Patent Number: 043361030
Section: description

Referring now to the drawing and first, particularly, to FIGS. 1 and 2 thereof, there are shown two cross-sectional views of a fuel element pit 1, mutually disposed at an angle of 90.degree. relative to one another. The work to be performed therein is able to be effected from a movable operating bridge 11 under visual observation. In these diagrammatic illustrations of FIGS. 1 and 2, only those tools and fixtures are shown diagrammatically as are required for performing the method of the invention. Thus, there are located at one side wall of the pit 1, a tilting device 12 for a fuel element receiving basket or cage 51, and also a storage container 13 for defective fuel rods, a supply storage 14 for new fuel rods as well as a so-called Sipping test device 19 for checking entire fuel elements for defective fuel rods that might be contained therein. A container 16 for disassembled fuel-element base or foot members, a fuel-rod exchanging tool 2 as well as a tool 18 for loosening the fuel-element foot members and a tool 17 for checking each individual fuel rod for possible damage are additionally provided. The operating sequence for the method of the invention is as follows: Each fuel element taken from the reactor core is initially introduced into the Sipping test device 19 and is examined there for possible damage to individual fuel rods. Should a fuel element 5 received therein be perceived to be defective, that fuel element 5 is placed in the receiving basket 51 of the tilting device 12. This receiving basket 5 is closable at both ends thereof. The fuel element 5, with this receiving basket 51, is then turned through 180.degree., so that the foot or base end of the fuel element 5 points upwardly. After the receiving basket 51 is opened at an end thereof, the base or foot member of the fuel element 5 is disassembled therefrom by means of the remotely activated tool 18 and is deposited in the storage container 16. The ends of the fuel rods in the fuel element 5, which are now freely accessible at the top of the latter, as viewed in FIG. 1, for example, are individually examined by means of the device 17, which is operatable, ultrasonically (German Published Non-Prosecuted Application DT-OS No. 2 414 650.1), for example, to detect any water leakage into the fuel rods. In this manner, the defective fuel rods are determined and can be removed from the fuel element 5. To this end, the centering plate 4, shown in top plan view in FIG. 4, is initially disposed above the fuel elements 5, the bore holes 42 of the centering plate 4 permitting accurate travel of the fuel-rod exchanging tool 2 to the respective fuel rods located underneath. This situation is schematically represented in FIG. 3. The fuel rod 52 perceived to be defective is withdrawn into the interior of the tool 2, through which water flows continuously during this operation, being drawn into the lower end of the tool 2 through a line 31 under the action of a pump 32. This measure provides the advantage that, in the case of fuel rods with cladding-tube damage that is so extensive that fission gases can escape, the escaping gases can be entrained by this flow of water upwardly within the tool 2, and the thus entrained gases can then be separated from the water in the gas separator 33 and fed to the purification and waste-gas collecting system 35. Thereafter, the defective fuel rod which is gripped and enclosed by the tool 2 is moved away by and with the latter and deposited in the container 13 for defective fuel rods. For this purpose, the pulling or drawing mechanism inside the tool 2, which may be of the rack-and-pinion type, for example, is switched over so that it then pushes the rod into the container 13, which is advantageously connected to a circulatory loop of water all its own, since it must be expected that the fuel rods stored therein give off radio-active fission gases and fission products. Then, a new fuel rod or another replacement rod can be taken from the store 14 of new fuel rods; in principle, this corresponds to the operation of removing the fuel rod from the fuel element. Thereafter, this new fuel rod is introduced into the vacated position in the fuel element 5. After the fuel-rod exchange operation is completed, the fuel element 5, which is now usable again, is temporarily deposited in a fuel-element storage rack 15 until it can be reinserted into the reactor core with the aid of the fuel-element loading machine. As mentioned hereinbefore, the centering plate 4 is an essential element of the fuel-rod exchanging device 2. This plate is shown in a top plan view in FIG. 4 and in a side elevational view in FIG. 5. The intersections of the coordinates a and b with A and B, respectively, represent corresponding fuel rod positions of a fuel element or fuel assembly. From FIG. 4 and also from FIG. 5 it is clearly evident that the fuel rods 52 are disposed very closely together. For this reason, it is not possible to provide centering holes in the centering plate 4 for each individual fuel rod position so that the fuel-rod exchanging tool 2 may be applied to the respective fuel rod. This difficulty is circumvented accordingly by providing that the centering holes 42 be assigned only to each fuel rod which corresponds to the coordinate intersections a, A. In order that all of the fuel-rod positions may be reached, this centering plate 4 is raised, turned through 90.degree. and replaced; then, the centering holes 42 correspond to fuel rod positions of the coordinate intersections a, B. A repeated similar shift through 90.degree. permits all of those fuel rods which are located at the coordinate intersections b, B to be covered and after turning once again through 90.degree., those fuel rods at the coordinate intersections b, A. The illustrted bores 43 are provided for receiving the threaded bolts or pins of the control rod guide tubes 53 and, likewise, illustrated connecting breakthroughs are provided between pairs of adjacent centering holes. The latter measure is necessary so that the threaded bolts or pins of the control rod guide tubes 53 are not in the way when the centering plate 4 is put in place after having been turnably shifted through 90.degree.. The position of the centering plate 4 per se must depend upon the fuel element or the receiving basket or cage 51 therefor. For this purpose, the centering plate 4 is provided with four spacer posts or pins 41 which carry the centering frame 44 proper that surrounds the wall of the receiving basket or cage 51. In this manner, assurance is provided that each centering hole 42 of the plate 4 is associated with one fuel-rod end in accordance with the coordinate scheme shown and described herein. These fuel rod ends, as shown, are provided with a mushroom-shaped head, which is surrounded by the gripper 61 as shown in FIG. 5. This gripper 61 is attached to a moving linkage 6 and thereby permits the withdrawal of the respectively gripped fuel rod 52, as shown in FIG. 5. An eddy current test probe 23 is built into the lower part 21 of this fuel rod exchanging tool 2, so that the exact location of any damage to this fuel rod 52 is immediately ascertainable as the fuel rod is being pulled through the tool 2 upon its removal from the fuel element 5. The fuel rod exchanging tool 2 per se is diagrammatically shown in FIG. 6. On the face of it, the tool 2 is formed of a lower part which is enclosed by an outer support tube 22 and of an upper part which is surrounded by a large guide tube 26. The length of the support tube 22 is somewhat greater than the length of the fuel rod 52 to be drawn in, and the length of the large guide tube 26 is of the same order of magnitude. At the end of this large guide tube 26 there is a console or bracket carrying a driving device 27 formed, for example, of a gear drive and a hand crank. This gear drive 27 meshes with a rack 65a, which is connected to an upper withdrawal tube 65. This tube 65 is connected to the moving linkage 6 proper, which extends through the support tube 22 and into the large guide tube 26 through a seal 25. At the lower end of the support tube 22, the moving linkage 6 extends advantageously through a closure member 21 of the suport tube 22 as well as through the eddy current measuring probe 23 installed therein. On the moving linkage 6, there is located the gripper 61 proper for the respective fuel rod head; it is slotted two to three times radially and is formed of springy or resilient material. As shown, the inner contour of the gripper 61 is matched to the conventional mushroom-shaped head of the fuel-rod end cap. After being placed on this cap, the gripper 61 is clamped to the cap by a locking or coupling rod 63 in a manner that it cannot be loosened from the fuel rod head, as the locking rod 63 is pushed downwardly. The rod 63 extends through the entire tool and is provided at the upper end thereof, as shown in FIG. 6, with a thread which threadedly engages in an adjusting nut 64. This adjusting nut 64 is virtually braced against the pulling tube 65 or the end closure thereof, which is provided with a hook for connecting a lifting tool or device thereto. The end 63a of the rod 6 is provided with two markings which indicate the upper and the lower position of this rod 6 and thereby also the inwardly driven and the outwardly driven conditions of the gripper 61. In the inwardly driven condition, the gripper 61 is closed and is locked against opening. In the outwardly driven condition, and upper conical member 62 at the locking or coupling rod 63 opens the gripper 61 by making contact with a slotted opposing cone or countercone 61a. In this manner, the gripping tool releases the fuel rod; is retractible and proceeds to another fuel rod. The hereinbefore described part of the fuel rod exchanging tool 2 exhibits the function thereof of pulling a fuel rod 52 out of a fuel element 5. For pushing a fuel rod 52 into a fuel element 5, however, it is necessary that the new fuel rod be kept free of any bending or buckling stress. For this purpose, an inner support tube 24 is provided, wherein the moving linkage 6 and, consequently, also the inwardly driven fuel rod 52 are guided. This guide tube 24 also ensures that, when the fuel rod 52 contained in this tool is pushed into the fuel element 5 or into the storage container 13 for the fuel rods 2, also, that no lateral movement of the relatively thin fuel rod 52 and consequent bending or buckling of the latter is possible due to the thrust or push exerted by the gripper head 61. Assurance is provided, in this manner, that a new fuel rod 52 can be reloaded without damage into a vacated fuel-rod position. Buckling or bending in the fuel element per se of the fuel rods 52 that are being inserted is prevented by the mesh of the spacers that are disposed at different levels of the fuel element. Instead of performing the raising and lowering operations manually, a motor drive may also be used, of course, however, it would appear that manual operation is preferable so that possible disturbances during the feed of the fuel rod 52 into and out of the fuel element 5 can be felt more readily. As already mentioned hereinbefore, the placing of the fuel rod exchanging tool 2 onto the centering plate 4 is controlled from above by visual observation. The tool 2 is suspended for this purpose from a suitably drivable lifting device. To provide weight relief, it is advantageous to provide the tool further with a float at an upper part thereof, as shown diagrammatically in FIG. 3 in the interest of clarity. It should not be left unmentioned that this special fuel-rod exchanging tool 2 is usable also for performing other operations in the fuel-element pit, such as for examining the individual fuel rods 52, for example, by so-called gamma scanning, to determine the burnt-off condition thereof, by leading them past an appropriate measuring head.