Patent GB-1022839-A (GB)
Title: Fuel assemblies for a nuclear reactor
IPC: G21C3/32
Filed: 1964-05-15
Abstract: 1,022,839. Fuel elements. WESTING- HOUSE ELECTRIC CORPORATION. May 15, 1964 [June 21, 1963 (2)], No. 20311/64. Heading G6C. A fuel assembly for a nuclear reactor comprises an elongated casing structure, a plurality of bundles of elongated fuel rods tandemly and slidably mounted within the casing structure, and structural means consisting at least in part of a material having a greater coefficient of thermal elongation than the fuel bundles and joining the latter so that they are displaced longitudinally from each other with an increase in temperature of the fuel assembly. In the embodiment shown in Fig. 1, two bundles 60a, 60b of fuel rods 66 are slidably located within a casing 22 between a pair of blanket fertile bundles 62, 64. The casing 22 is provided at its lower end with a flow nozzle assembly 24 and at its upper end with a spoke mounted manipulator lifting hook 26. The nozzle assembly 24 includes a pair of nested concentric tubular members 36, 38, the outer tube 38 being slidably mounted on the inner tube 36 while the latter is secured to a thickened portion 40 welded to the casing 22. In order to provide shock-absorbing action when the fuel assembly is loaded into a reactor core, the outer tubular member and a stop member 46 secured to it are biased away from the adjacent end of the fuel assembly by spring 44. Within each fuel bundle 60a, 60b, the rods 66 are joined laterally to one another by means of a plurality of ferrules 80 which are spaced along the length of each bundle and brazed to adjacent rods 66 so that each bundle is assembled into a rigid beam-like structure. The outer ends of the fuel bundles 60a, 60b are provided with partial end plates 102, 104, respectively, of cruciform configuration and connected one to the other by a supporting rod 112 which extends longitudinally and centrally through both the fuel bundles 60a, 60b. The rod 112 is fabricated from a cermet such as UO 2 -stainless steel or PuO 2 -stainless steel, from fuel-bearing alloys such as U-Mo or from fissium, while the fuel rods 66 are fabricated from stainless steel cladding tubes filled with pellets of UO 2  or PuO 2 -UO 2 . The thermal elongation of the rod 112 is substantially greater than that of the fuel rods 66. Adjacent the respective outward end portions of the fuel bundles 60a, 60b, a plurality of peripheral straps 82 are secured at spaced locations as by brazing and located on each is a plurality of positioning dimples which serve to locate the associated fuel bundles 60a, 60b coaxially within the casing 22 and to prevent lateral movement of their outward end portions. Adjacent the juxtaposed end portions of the fuel bundles 60a, 60b, a plurality of corner straps 88 are secured, each being provided with a pair of stabilizing leaf-springs (not shown), while corner straps 92 are secured to each juxtaposed end of the fuel bundles 60a, 60b, each being provided with a finger-like spring projection. The positioning dimples 84 are absent from the corner straps 88, 92 and thus substantially one-half of each fuel bundle 60a or 60b is free to bow or bend laterally relative to the casing 22 against the action of the stabilizing springs and the spring projections. The rod 112 is slidably and resiliently mounted through the fuel bundles 60a, 60b by means of a plurality of resilient rings 132 spaced at intervals along and closely engaging the surrounding fuel rods 66. Each ring 132 is provided with a plurality of stabilizing leafsprings which resiliently engage the rod 112. With an increase in temperature of the fuel assembly the rod 112 elongates to a greater extent than do the fuel bundles 60a, 60b and consequently the gap 96 between the bundles increases. This increased separation of the chain reacting masses operates to introduce a negative temperature coefficient of reactivity into the chain reacting system. The fuel assemblies are particularly contemplated for use in fast reactors or other reactors having a net positive coefficient of reactivity. For ceramic fuel with a cermet or metal alloy supporting rod, i.e. where the rod is not clad, rapid changes in power level, sufficient to double the reactor power output in a few seconds or less, result in the thermal expansion of the supporting rod commencing before that of the tubes enclosing the fuel. This occurs because the heat is generated directly within the supporting rod while in the fuel rods it is generated in the ceramic material and must be transferred to the cladding material. The displacement of fuel from the core centre is thus greater during fast transients than during slow changes in power level.