Patent Number: 047056630
Section: description

Referring now to the figures of the drawings in detail and first, particularly, to FIGS. 1 and 2 thereof, there is seen a square grid-shaped or latticed spacer 2 formed of a nickel-chronium-iron-alloy which belongs to a nuclear reactor fuel element for a pressurized water nuclear reactor. Two flat, planar outer webs 3 and 4 can be seen which are disposed edgewise at right angles to each other. Disposed on the inside of these outer webs 3 and 4 are inner webs 31 to 33 parallel to the outer web 3, and inner webs 41 and 42 parallel to the outer web 4, which cross each other at right angles forming square grid meshes or mesh openings. A control rod guide tube or a fuel rod of the nuclear reactor fuel element containing nuclear fuel, is engaged in a respective opening. The inner and outer webs are at right angles to the control rod guide tube or fuel rod and both the outer webs 3 and 4 and the inner webs 31 to 33 and 41 and 42 flatly face the control rod guide tube or fuel rod. For the sake of clarity, only one single fuel rod 5 is shown in the corner grid mesh opening 6 of the spacer 2 located between the two outer webs 3 and 4. The lateral surfaces of the edgewise inner and outer webs are parallel to the longitudinal direction of the fuel rod 5. The control rod guide tubes penetrating the other grid mesh openings of the spacer 2 and the fuel rods containing the nuclear fuel, are parallel to the fuel rod 5. Each of the control rod guide tubes is detachably connected at one end thereof to a non-illustrated cover plate of a cover part, e.g. with a screw connection, and is connected at the other end thereof to a non-illustrated base plate of a base part of the nuclear reactor fuel element. The control guide rod tubes penetrate the cover and base parts at right angles. The cover and base plates are also square. The fuel rods which engage a respective one of the grid mesh openings of the spacer 2 and which contain nuclear fuel in gas-tightly sealed cladding tubes formed of a zirconium alloy, are secured neither to the cover plate nor to the base plate of the nuclear reactor fuel element, but instead they have clearance in the longitudinal direction between the cover and the base plates and they can therefore freely expand along the direction of their longitudinal axes, i.e. in the longitudinal direction of the fuel element. Inside the square grid mesh openings, the inner webs 31 to 33 and 41 and 42 of the spacer 2 have non-illustrated springs and fixed knobs which are respectively directed inwardly into the grid mesh openings through which the fuel rods are guided. These springs and knobs support these fuel rods in a force-locking manner on the latticed spacer 2. The latticed spacer 2 is in turn supported in a form-locking manner on control rod guide tubes guided through individual grid mesh openings. A form-locking connection is one which is accomplished by the shape of the parts themselves, while a force-locking connection requires outside force. On the outer webs 3 and 4 there can be seen a spring 7, 8 directed into the corner grid mesh 6 of the spacer, which supports the fuel rod 5 on the spacer 2 in a force-locking manner. On the edges that are at right angles to the mutually parallel control rod guide tubes and fuel rods in the spacer 2, the outer webs 3 and 4 have deflector or guard vanes 9 and 10 that are curved slightly inward. The spacer 2 has an outwardly curved quarter circle curve 11 on the outer corner of the corner grid mesh opening 6 located between the outer webs 3 and 4. The curve 11 is formed from these two outer webs 3 and 4 with an overall equal radius of curvature curved around the same directional axis which is parallel to the longitudinal direction of the control rod guide tubes and the fuel rods in the spacer 2. The two outer webs 3 and 4 form the curve 11 with a one-piece angular part 12 which is secured at a location 13 or 14 to an elongated remaining part of each of the two outer webs 3 and 4. These locations 13 and 14 are located on outer grid mesh openings 15 and 16 adjacent the corner grid mesh opening 6 and are therefore spaced from the curve 11. The locations 13 and 14 are oblong and parallel to the longitudinal direction of the control rod guide tubes and the fuel rods in the spacer 2. At these locations 13 and 14 the angular part 12 overlaps the extended remaining parts belonging to the outer webs 3 or 4. The angular part 12 is welded to the remaining parts at the locations 13 and 14. The edges of the outer webs 3 and 4 which are at right angles to the longitudinal direction of the control rod guide tubes 5 and the fuel rods in the spacer 2 change over at the curve 11 into edges 17 and 18 defining channels, chamfers or niches 22 and 23. At these edges 17 and 18 of the channels 22 and 23 and at the curve 11, the outer webs 3 and 4 or the angular part 12 of these outer webs 3 and 4 are drawn inward toward the fuel rod 5 penetrating the corner grid mesh opening 6 and therefore form respective bevels 19 and 20 at these edges 17 and 18. The bevels 19 and 20 run in the longitudinal direction of the fuel rod 5 toward the end of the fuel rod 5 which is located on the side of the cross section of the spacer on which the edges 17 and 18 with the bevels 19 and 20 are also located. The spacers 2 of two mutually parallel nuclear reactor fuel elements are disposed diagonally next to each other in a reactor core like chess board squares. Before a relative movement of the nuclear reactor fuel elements in their longitudinal direction, curves 11 on the outside of the fuel rod 5 of the respective diagonally adjacent nuclear reactor fuel elements initially lie against each other. During the course of this relative movement, the two spacers 2 of the adjacent nuclear reactor fuel elements meet, and the bevel 20 of the spacer 2 of one nuclear reactor fuel element can slide on the bevel 19 of the spacer 2 of the other nuclear reactor fuel element without catching against edges of the outer webs of the spacers 2, until finally the curves 11 of the spacers 2 of the two nuclear reactor fuel elements lie next to each other and touch, as shown in FIGS. 3 and 4. By means of the bevels 19 and 20 of the spacer 2 according to FIGS. 1 to 4, not only is hooking of adjacent nuclear reactor fuel elements prevented during loading of a pressurized water nuclear reactor, but the outer corner of the corner grid mesh opening 6 located between the outer webs 3 and 4 is also stiffened, reinforced or strengthened. The foregoing is a description corresponding in substance to German application No. P 34 43 861.0, dated Nov. 30, 1984, the International priority of which is being claimed for the instant application and which is hereby made part of this application. Any material discrepancies between the foregoing specification and the aforementioned corresponding German application are to be resolved in favor of the latter.