Patent Number: 041558073
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENTS As shown in FIG. 1, the core 10 of a nuclear reactor is typically made up of a plurality of elongated fuel assemblies 12. In a typical pressurized water reactor (PWR), for example, the assemblies 12 are supported at the bottom by a lower core plate 14 and are supported at the top by an upper core plate 16. These plates 14, 16 are simple supports for the assemblies 12, generally including a pin-in-hole 17 configuration, which fix axially and radially the location of the upper nozzle 18 and lower nozzle 20 (FIG. 2) of each assembly. The assemblies 12, however, may have radial displacement, during reactor operation, along their length, as a result of flow and temperature induced forces. Prior to reactor operation, the assemblies 12 are loaded into the core 10 closely adjacent one another, and surrounded by a core barrel 22 for former assembly 24. Reactor coolant typically enters the reactor vessel 26 through an inlet nozzle 28, passes down the annular region between the vessel 26 wall and the core barrel 22, is turned 180.degree. in the lower portion of the vessel, passes up through the core 10 at a high velocity, on the order to fifteen feet per second, and exits through the outlet nozzle 30. A typical fuel assembly 12, shown in FIG. 2, comprises a plurality of coextending fuel rods 32 supported at either end by the upper nozzle 18 and lower nozzle 20, and horizontally spaced from one another by spacing means, such as the grids 34 at a plurality of core elevations. The term "core elevation," when used herein and in the appended claims, refers to the axial position within the core that corresponds to the position of a spacing structure or grid, along the assembly length, including the height of the grid outer element, such as a strap 36; for example, if a grid horizontal centerline is positioned fifty inches up from the top of the bottom nozzle, and the height dimension of the outer element of the grid is four inches, then that position between forth-eight and fifty-two inches up from the top of the bottom nozzle is the core elevation. A typical fuel rod 32 includes a plurality of uranium bearing fuel pellets 38 axially stacked within a rod cladding 40 which is hermetically sealed at both extremities by end plugs 42. A typical fuel rod 32 may be as much as sixteen feet in length, or greater, with an outside diameter in the range of one-half inch. The grids 34 function not only to maintain proper lateral alignment and spacing among the rods 32 within a fuel assembly 12, allow for axial growth during reactor heat-up and operation, and control coolant flow, but also to alleviate rod-to-rod contact among fuel rods of the same assembly and also among rods of adjacent fuel assemblies 12. Matched grid core elevations among adjacent assemblies also alleviates concerns regarding coolant cross-flow induced vibration and local flow starvation. It is critical to ensure that any contact among adjacent fuel assemblies 12, which may have a tendency to vibrate and slightly bow, be of a grid-to-grid variety. If such contact is not maintained, there is a likelihood of fretting damage or flow starvation at the point of contact of a rod 32, particularly outermost rods, with another rod 32 or another grid 34. Fretting could possibly lead directly to breach of the cladding 40, and flow starvation could create a local hot spot leading to local cladding 40 melting. Local melting could further lead, in the extreme case, to breach of the cladding 40, thereby allowing reactor coolant to enter the rod, and also allowing the nuclear fuel or fission products to enter the reactor coolant. For these reasons, all the fuel assemblies 12 within a typical core include spacing structures, or grids, at the same core elevations. A typical grid 34 is shown schematically in FIG. 3. As the art of grid and fuel assembly structures is quite crowded, it is to be understood that the instant invention is compatible with most, if not all, fuel assemblies and grid structures in the art, and is not to be limited by the examples discussed herein. A typical grid 34 is an "egg-crate" type structure, manufactured from a plurality of inner straps 44 and outer straps 36 which form a plurality of grid cells 46. Each cell 46 typically includes support means 48 and spring means 50 which support the rod 32 within the cell 46 while allowing some axial and radial expansion. Also typical are components such as mixing vanes 51 and guide tabs 53, among others. During manufacture of one type of fuel assembly 12, a plurality of cylindrical sleeves 52, which typically extend above and below the grid straps 36, 44, are brazed into each grid 34 at given cell locations. The grids are subsequently aligned in a fixture, and thimble tubes 54 inserted through the aligned sleeves 52. A tool is then inserted through each thimble tube 54 which expands the tube 54 at the sleeve 52 locations, thereby fixing the core elevation of each grid 34. Other means of fixing the grid core elevation may be used. The thimble tubes 54 are typically used for insertion of control elements 56, as shown in FIG. 2. As discussed above, all assemblies 12 within a core 10 typically include grids 34 at the same core elevation. However, with increasing technology, there is a likelihood that the number of grids 34, the core elevation of grids 34, or the height of the grids in a given core 10, may desirably be modified. Although the grids 34 are typically composed of a low neutron absorption cross section material, such as alloys of zirconium, they do present a parasitic barrier to nuclear efficiency. It is therefore desirable to minimize the amount of grid material in a core. Also, operating experience may show the desirability of added grids for assembly support and to minimize fuel rod bowing, particularly in the lower portions of the assembly. Similarly, grids may be deleted. It will be well recognized that since a core 10 typically is divided into a plurality of regions into which the assemblies 12 are placed and shuffled during refuelings such that a given assembly may be placed in, for example, three different core locations during its operating lifetime, a significant penalty would result if, because of grid core elevation incompatiblity, assemblies 12 would have to be removed from the core 10 and modified or reprocessed prior to obtaining design burnup. The instant invention provides a core and transition fuel assembly which may be utilized without modifying any other fuel assemblies 12 within the core. The transition assembly provides a spacing structure such as a grid 34, or a grid extension, or a partial grid-like structure, at each core elevation where other fuel assemblies in a given core have a grid 34. The following example is based upon a core 10 which initially includes assemblies 12 with grids 34 at seven core elevations, and is desirably modified to include fuel assemblies 12 with grids 34 at eight core elevations. The basic principle of the instant invention is, however, equally applicable to a decreased number of grids, or merely a change in core elevation of the same number of grids. This example, therefore, is to be viewed as illustrative, and not in a limiting sense. The cored is divided into three core regions, denoted by the letters "A," "B," and "C" on FIG. 4. All three regions initially include seven-grid assemblies when, for example, it becomes desirable to change to assemblies having eight grids. At the next refueling, region "C," which has achieved its desired operating life, is removed for reprocessing. Region "B" fuel assemblies are then shuffled into region "C," and region "A" assemblies are shuffled into region "B." Transition fuel assemblies are then placed in region "A". The transition assemblies are thus placed adjacent region "A" and region "B" assemblies, such that any contact is of a grid-to-grid variety. At the next refueling, region "C" assemblies (seven-grid) are removed, region "B" assemblies (seven-grid) are shuffled to region "C," region "A" transition assemblies are shuffled to region "B," and fresh eight-grid assemblies are placed in region "A." The transition assemblies not maintain contact with both eight-grid and seven-grid assemblies in a grid-to-grid fashion. Dependent upon the core loading pattern, there may be some locations, particularly at the outer portions of the core, where a region "A" assembly (eight-grid) would be adjacent a region "C" assembly (seven-grid), as shown by the dotted line on FIG. 4. At such locations, second transition assemblies would have to be inserted in place of the fresh region "A" (eight-grid) assemblies. The transition assemblies placed in region "B" are subsequently shuffled into region "C," and finally out of the core for reprocessing. The second transition assemblies would subsequently be shuffled into region "B" and then region "A." Upon discharge, the core will the contain only eight-grid assemblies. Because the exact number of assemblies may vary slightly among core regions, there may be instances where one or more assemblies may have to be prematurely discharged, but not premature removal of a whole region or a whole core. One embodiment of a transition assembly for the example seven-grid to eight-grid changeover is schematically shown in FIG. 5. The rectangles represent the core elevations of the grids on the three types of assemblies. In this instance, all of the grid core elevations of the eight-grid assemblies are different than the grid core elevations of the seven-grid assemblies, without overlap. If the grids of the two types are all of the same height, the transition assembly can comprise fifteen grids, also of the same height. If the eight-grid assembly grid height is different from the seven-grid assembly grid height, the transition assembly can comprise seven grids corresponding to the seven-grid assembly, and eight grids corresponding to the eight-grid assembly. It is unlikely, however, that the grid core elevations would not overlap or be within several inches of another at some elevations. FIG. 6 represents these conditions. The eight-grid and seven-grid assembly grids are of the same height, although they may also be different, and the transition assembly comprises nine grids, designed "A" through "I." Grids "A," "D" and "I" may, in this example, be identical to the eight-grid and seven-grid assembly grids in respective core elevation and design. Grids "F," "G," and "H" could also be identical in core elevations with the respective aligned seven-grid assembly grids and eight-grid assembly grids, or as discussed further below, may comprise auxiliary grid structures. Grids "B," "C," and "E" may comprise extended grid structures, also discussed below. FIG. 7 shows a grid structure referred to above as an extended grid structure. As shown, it is generally similar to a typical spacing structure or grid 34, with the addition of vertically extended outer strips 36. A separate piece attached to a standard grid may also be used. The straps are enlarged in the height dimension to maintain grid-to-grid contact among fuel assemblies 12 with grids 34 at relatively close or overlapping core elevations. To minimize the amount of neutron parasitic material in the core, the extended grid may include openings 58. As the extended portion of the outer strap 36, which may be above, below, or above and below the standard portion of the grid, does not necessarily have to provide significant structural ability to the grid, the openings 58 do not detract from necesary structural integrity. It is desirable, however, to orient the openings 58 such that the outermost portions of the outer fuel rods remain enclosed by the extended portion of the outer straps 36. Depending upon the amount of extension necessary, inner butresses 60 may be used to minimize any vibration of the extended portion. The butresses 60 may be separate components, or extensions of the inner straps 44 brazed to the outer straps 36, as shown. FIG. 8 shows a grid structure referred to above as an auxiliary grid structure, as may be used at the locations "F," "G," and "H" of FIG. 6. Here, an auxiliary grid 62 is spaced apart from and affixed to a typical spacing grid 34 by partially extended outer straps 64, which may be integrally formed with the standard grid outer strap 36. They may also be a separate component affixed to the outer strap 36. Partially extended refers to the fact that only a portion of the outer strap 36 is extended upward, or downward, or both, preferably at the strap 36 extremities, thereby minimizing the amount of added parasitic material. Stiffening means 66, such as a punched section or an attached member may be used to increase structural strength. The auxiliary grid 62 further includes at least several auxiliary inner straps 68 to maintain necessary support. Grid-to-grid contact at the auxiliary grid is desirably transmitted to four or more thimble tubes 54 through the partial grid network formed by the straps 68 and through the auxiliary sleeves 70. The sleeves 70 may be brazed to the straps 68. The auxiliary grid may also include partial support straps 71 to provide additional support to the upper horizontal portion 72 of the partially extended outer straps 64. A plurality of inner straps extending across the auxiliary grid 62 would unnecessarily add parasitic material to the core. Other means of affixing the auxiliary grid to the assembly, at a given core elevation, may be utilized. Although the auxiliary grid 62 is shown in FIG. 8 extending above a typical spacing grid, it could alternatively extend above, below, or both above and below the grid. Further, the auxiliary grid 62 may include any of the features typically included in a spacing structure, such as retention means, spring means, mixing vanes, and guide structures, among others. FIG. 9 shows another auxiliary grid structure. In this instance, the auxiliary grid is spaced from and affixed to a typical spacing grid 34, and hence the assembly, by extended sleeves 72. The thimble tubes 54 are expanded at locations inside the extended sleeves 72, which are brazed to the auxiliary inner straps 68. The features of the auxiliary grid 62 may include any of those discussed in reference to FIG. 8, above. An advantage of the structure shown in FIG. 9 is that it eliminates a number of full length inner straps by utilization of the auxiliary straps 60 and partial straps 71. It is therefore seen that the instant invention provides a core and a transition fuel assembly which may be used in a nuclear core with fuel assemblies that include spacing structures or grids at differing, or overlapping, core elevations. Although several example grid structures and transition assemblies have been discussed, it will be apparent that many modifications and variations are possible in view of the above teachings. It is therefore to be understood that within the scope of the appended claims, the invention may be practiced other than as specifically described.