Patent Number: 041347900
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENTS Referring first to FIG. 1, there is illustrated a typical nuclear reactor vessel 10 and reactor vessel closure head 12. The reactor vessel is typically vertically disposed in a concrete reactor cavity 13 and connected to other components of the nuclear steam supply system (not shown) by means of a reactor coolant inlet nozzle 14 and outlet nozzle 16. Most of the components internal to the reactor vessel 10 are supported directly or indirectly by the core support barrel 18 which is suspended from and firmly engaged between the closure surface between the vessel head 12 and the top of the reactor vessel 10. The core support assembly 20 rests on the bottom of the core support barrel 18 and the core support plate 22 rests on top of the core support assembly 20. The core support plate 22 serves to support and align a plurality of fuel assemblies 24 which are also aligned at the top by the upper core alignment plate 26. Alignment of the assemblies 24 at the top and bottom is typically effected by means of fuel assembly end fittings (not shown) which are adapted to mate with end fitting receiving means (not shown) on the core support plate 22 and the upper core alignment plate 26. During normal reactor operation, a liquid coolant enters the vessel through inlet nozzle 14 and follows the flow path 32 down the outside of the core support barrel 18 and up through the core support assembly 20 which structures are adequately orificed for such flow. The coolant continues upward through the fuel assemblies 24 where mixing grids (not shown) and thousands of individual fuel rods (not shown) produce large flow resistances tending to push the fuel assemblies 24 towards the upper core alignment plate 26. The alignment plate 26 is typically restrained from moving upwards by the downward force of the upper guide structure support plate 30 transmitted through a plurality of control rod shroud tubes 28 welded to the upper guide structure support plate 30 and the upper core alignment plate 26. The upper guide structure support plate 30 is suspended from and firmly engaged between the closure surface of the vessel head 12 and top of the reactor vessel 10. The upper core alignment plate 26 is orificed to permit coolant to enter the region of the control rod shroud tubes 28, but the upper guide structure support plate 30 is essentially integral so that the coolant flow continues on the flow path 32 through the outlet nozzle 16. Each control rod, only one of which 29 is shown, must have a clear path for insertion and withdrawal over the entire vertical extent of the fuel assemblies 24. This is accomplished by providing control rod shroud tubes 28 connected with control rod guide tubes (not shown) in the fuel assemblies 24. Referring now to FIGS. 2 and 4, a typical fuel assembly 31 includes five vertically extending zircaloy control rod guide tubes 38 to which are welded stainless steel upper and lower end fittings 34 and 44, respectively, and a plurality of axially disposed rectangular fuel spacer grids 42. These grids maintain the lateral spacing of the plurality of nuclear fuel rods 40 while permitting a limited amount of axial motion resulting from fuel rod expansion. Each fuel rod is welded at its bottom to the top of the fuel assembly lower end fitting 44. The bottom of each guide tube 38 is also welded to the top of the lower end fitting 44. Four vertically extending and equally spaced fuel assembly alignment posts 46 are welded to the bottom of the fuel assembly lower end fitting 44 and support the entire weight of the fuel assembly against the core support plate 22. Fuel assembly alignment pins 52 extend upward from the core support plate 22 and are located in a uniform array on the core support plate such that each alignment pin 52 can be slidably received by the fuel assembly alignment post 46 on one corner of each of four fuel assemblies 31 properly located on the core support plate 22. When the fuel assembly alignment posts 46 are properly positioned on the core support plate 22, the latch 56 on the cantilever leaf spring 48 attached to the fuel assembly alignment post 46 with attachment means 50 engages a recessed region 54 in the fuel alignment pin 52. When it is desired that the fuel assembly be removed from the core or relocated, the usual steps of unbolting and removing the reactor vessel head 12 and lifting the upper guide structure support plate 30 are followed. As described above, the control rod shroud tubes 28 are welded to the upper core alignment plate 26 and to the upper guide structure support plate 30 so that when the support plate 30 is lifted from the reactor the alignment plate 26 is also removed, exposing the upper end fittings 34 of all the fuel assemblies 24. To remove a fuel assembly from the core, the assembly is grasped at the upper end fitting 34 by the grappling tool on the refueling machine, which is customarily provided in all reactor installations. An upward force of about 3,000 pounds is required to overcome the hold-down force between the latch 56 and the recessed region 54 and to lift the fuel assembly out of the reactor. This force is well within the capabilities of a typical refueling machine. A new or relocated fuel assembly can now be inserted in the location vacated by the removed assembly. The refueling machine lowers the new assembly into position between the four corner fuel alignment pins 52. The latch 56 of each cantilever spring 48 in its relaxed position will contact the upper portion of the fuel alignment pin 52. As the assembly continues to be lowered, each spring 48 will be deflectively loaded by the weight of the fuel assembly. As the fuel assembly alignment posts 46 contact the core support plate 22, each spring latch 56 snaps into engagement with the recessed region 54 on the fuel alignment pin 52. The grappling tool on the refueling machine is then released and withdrawn from the reactor. After all assemblies have been placed in their proper positions, the upper core alignment plate 26 is repositioned over the fuel assembly upper end fittings 34. Proper alignment of the fuel assembly is maintained by the sliding engagement of the upper fuel assembly alignment pins 36 into the recesses 37 in the upper core alignment plate. These recesses are large enough to accommodate the axial expansion of the control rod guide tubes 38 during core operation. The upper core alignment plate 26 is then firmly held in place when the vessel head 12 is tightened down. In the preferred embodiment, only two non-diagonal fuel assembly alignment posts of the four in any given assembly are fitted with the cantilever spring 48. When the assembly is in place on the core support plate 22 and each latch 56 is engaged in the recessed region 54 associated with these two non-diagonal posts, the horizontal component of the loaded spring force is sufficient to produce a very tight contact between the other two non-diagonal alignment posts 46' and associated alignment pins 52'. The net outwardly directed horizontal forces against the four fuel alignment pins 52 and 52' associated with a given fuel assembly are sufficient to preclude significant lateral motion of the assembly during core operation. The relationship of the fuel assembly alignment posts 46 to the fuel alignment pins 52 is more fully illustrated in FIG. 3. The square fuel assembly lower end fitting 44 has a ribbed internal structure 45 to permit upward flow of coolant through the assembly and has the five control rod guide tubes 38 welded in a symetric pattern with the bottom end open to receive the coolant flow. A fuel assembly alignment post 46 is welded to the bottom of the lower end fitting 44 near each corner. The shape of the fuel assembly alignment post 46 is designed to slidably engage the fuel alignment pin 52, one of which is shared by four assemblies. Cantilever springs 48 are attached to two non-diagonal alignment posts 46 through bolt means 50. The other two non-diagonal alignment posts 46' are held firmly against alignment pins 52' by the horizontal force component of the cantilever springs as described above. Referring now to FIG. 4, the fuel assembly alignment pin 52 has an upper cylindrical portion connected to a lower cylindrical portion of smaller diameter by a recessed region 54 having a downwardly inclined annular surface at an angle of approximately 30.degree. with the horizontal. The alignment pin 52 is permanently and rigidly attached to the core support plate 22. The fuel assembly alignment post 46 is shown in the proper position whereby the fuel assembly will be held down during core operation. The alignment post 46 extends vertically in parallel with and in close proximity to the upper portion of the alignment pin 52. A cantilever leaf spring 48 is attached to the upper portion of the fuel assembly alignment post 46 by bolt means 50 and extends downward along the side of alignment post 46 that faces away from alignment pin 52. At an elevation above the core support plate 22 slightly above the elevation of the recessed region of the alignment pin 54, the alignment post 46 has a cut-out passageway 47 extending downward far enough to permit the cantilever leaf spring latch 56 to protrude above the side of the alignment post 46 that faces alignment pin 52. The latch 56 has an inclined surface 58 which makes an angle with the horizontal substantially the same as the angle of the recessed region 54. In the locked position illustrated in FIG. 4, the cantilever spring 48 has a loaded deflection of about 0.089 inches, resulting in a horizontal force of about 450 pounds applied to the inclined surface 58. The vertical load on spring 48 required to disengage latch 56 is approximately 4,180 pounds. The maximum deflection of the cantilever spring 48 occurs during insertion and removal of the fuel assembly when the latch 56 is in contact with the upper portion of the fuel alignment pin 52, resulting in a total spring deflection of 0.189 inches. These dimensions are representative of a typical application wherein the fuel assembly lower end fitting is approximately 8.2 inches square and the length of the fuel assembly alignment post is approximately 5 inches. The spring 48 can be designed to either lock and force the alignment posts 46 down against the core support plate 22, or a slight gap may be permitted to exist during core operation. In this case the fuel assembly 30 would lift until the latch 56 contacts the recessed region 54. Because the springs provide a vertical friction force there results a certain amount of hysterisis which prevents vertical chatter. Referring now to FIG. 5, an alternate embodiment of the invention is shown wherein the cantilever leaf spring 48 is attached to the side of the fuel assembly alignment post 46 that faces the alignment pin 52. As shown in FIG. 6, another embodiment of the invention includes a horizontally disposed coil spring 60 for augmenting the force of the cantilever spring 48 on latch 56. It is contemplated that a person of ordinary skill in this art could adjust the length or material of cantilever spring 48 or the angles on the inclined surfaces 58 and 54 to achieve the desired combination of vertical hold-down forces and horizontal stabilizing forces between the latch, pins, and posts. In the preferred embodiment each latch provides both vertical and horizontal force components. The desired horizontal force, however, should not be so large as to require more downward force for actuating the locking mechanism than is provided by the weight of the fuel assembly itself, since any additional force would result in an undesirable compression of the control rod guide tubes 38. Furthermore, the present invention is not limited to the use of cylindrical alignment pins 52 or any particular shape of fuel assembly alignment post 46. For example, the alignment posts 46 can be adapted to perimetrically surround the alignment pins 52. It is further contemplated that a person of ordinary skill in this art could practice the invention by attaching the spring to the alignment pin to mate with a recessed region on the alignment post.