Patent Number: 055240313
Section: description

DETAILED DESCRIPTION Referring to FIG. 1, a bottom entry nuclear fuel assembly 10 typical of boiling water reactors is shown. The assembly includes a number of nuclear fuel rods 11 disposed between an upper tie plate 12 and a lower tie plate 13. Inlet nozzle 15 contains an orifice 17 which is surrounded by a three pronged guide 19. Each fuel assembly rests on a fuel assembly support plate 100 having an orifice 101 for the inlet of coolant water to the fuel assembly. Fuel assembly support plate 100 is located laterally by core support plate 110 and supported vertically by control rod guide tube 120. When the fuel assembly is within the core and located in its proper location within the fuel assembly support plate, three pronged guide 19 of the fuel assembly is located within assembly support plate 100. FIG. 2 is an enlarged view of the lower portion of the fuel assembly 10 shown in FIG. 1. FIG. 3 is a bottom view of the fuel assembly 10 showing three pronged guide 19, inlet nozzle 15 and inlet orifice 17. The following described embodiments discuss various debris filters as well as the method of modifying the fuel assembly and attaching a debris filter to an irradiated boiling water reactor nuclear fuel assembly to trap debris carried by the coolant. Referring to FIGS. 4A and 4B, the fuel assembly initially has a portion of the inlet nozzle and the three pronged guide shown in FIGS. 1-3 removed by cutting the inlet nozzle along cut line Z--Z shown in FIG. 2. Cutting the inlet nozzle to remove the three pronged guide enables the inlet nozzle to receive a removable, reusable and interchangeable debris filter of appropriate design. Cutting is accomplished with typical tools such as underwater saws or electrodischarge machining available to those skilled in nuclear fuel assembly repair. The resulting modified inlet nozzle 15' is slightly shorter than that of inlet nozzle 15. Although inlet nozzle 15 is shown cut along line Z--Z for purposes of illustration, it is readily understood that the lower nozzle 15 can be cut at any other location to remove the three pronged guide leaving the lower nozzle otherwise intact. Thus, in an alternative embodiment, the three prong guide is removed by cutting each of the three prongs flush with the nozzle at cut line Y--Y shown in FIG. 2. Referring to FIG. 5, a debris filter 50 to be inserted through the orifice 17 and into the open space 18 (FIG. 4A) within the fuel assembly inlet and attached to the inlet nozzle 15' is shown. Debris filter 50 includes debris filter cap ring 52 which forms coolant entrance orifice 53. Extending from filter cap ring 52 is filter replacement three pronged guide 54. In the embodiment shown in FIG. 5, filter replacement three pronged guide 54 is the same configuration, size and geometry as the removed three pronged guide 19. In alternative embodiments, either the replacement three pronged guide can be eliminated or its configuration, size or geometry changed if so desired. Connected to filter cap ring 52 is debris filter support ring 56 to which the filter media 58 is secured. Filter media 58 can be fabricated in a variety of shapes including for example cylindrical and fluted (FIGS. 6A, B, C) and can be made of perforated sheet metal, wire mesh, coarse screen, louvered blades. Examples of louvered blade filter media include angled blades (FIG. 7A), straight blades (FIG. 7B), chevron blades (FIG. 7C), and curved blades (FIG. 7D). Referring to FIG. 9A, filter media 58 comprises an assembly of louver blade disks 60 and spacer washers 62 stacked on guide rods 64 which are attached to filter support ring 56 (FIG. 9B) and welded to form a rigid structure as shown in FIG. 8. Referring to FIG. 10, fuel assembly 10 with a portion of the lower nozzle and three pronged guide removed (15') is shown with debris filter positioned within the inlet region of the fuel assembly. Filter cap ring 52 is flush against modified inlet nozzle 15'. Debris filter 50 is positioned and aligned within the fuel assembly by debris filter support ring 56 which sits within modified inlet nozzle 15' and by filter cap ring 52 which sits against the outer lip 16' of modified inlet nozzle 15'. Since coolant flow is from the bottom into the fuel assembly, the direction of coolant flow will bias the debris filter against the modified inlet nozzle. To maintain the debris filter to the assembly during refueling or handling and movement of the fuel assembly, springs 59 which are connected at one end at debris filter support ring 56 (FIGS. 5, 8, 9B and 10) secure the debris filter in place within the modified nozzle 15'. Preferably, springs 59 are made of Inconel or other material of suitable mechanical strength and resilience. Alternatively, other mechanical securing devices can be employed. If the debris filter is not intended to be removed from the fuel assembly at some later date, it can be welded to the modified inlet nozzle. The external dimensions of the fuel assembly with debris filter 50 installed are unchanged from that of the fuel assembly before being modified. The portion of the debris filter which extends beyond the modified nozzle 15' (i.e. filter ring cap 52 and three pronged guide 54) is substantially the same size as the portion of the nozzle removed by cutting along line Z--Z. Thus, modifications to the reactor core, core support plate, spent fuel storage racks, fuel elevators and other fuel assembly handling and storage apparatus or operating and refueling procedures are not necessary. Furthermore, since the debris filters are removable and reusable, periodic inspection, removal of debris, and interchange from one assembly to another is thereby permitted. In yet further alternative embodiments, debris filter 50 includes the addition of loosely packed metallic ribbons or coils (not: shown) in the interior of the filter media 58 to further trap and retain debris which would become entangled by the metallic ribbons. The efficiency of debris filter 50 can be increased by altering the filter area of filter media 58. For example, a cylindrical design filter (FIG. 5) can provide substantially greater filter area (which is limited only by the internal dimensions of the inlet nozzle) compared to the area of the orifice 17 in inlet nozzle 15. The filter shown in FIG. 5 has a filter area of approximately 45 in.sup.2 as compared to the cross-sectional area of orifice 17 which is approximately 7 in.sup.2. Thus, a very high efficiency can be employed by increasing the surface area of the filter media 58 without incurring an excessively high pressure drop. The pressure drop of debris filter 50 can be designed to be a predetermined value by varying design variables such as thickness, spacing, angle, and type of filter blades. The ability to select and thereby vary the pressure drop across the inlet nozzle of the fuel assembly as a result of utilizing the debris filter provides the ability to adjust the flow rate to selected assemblies in a given core. Accordingly, the ability to select a pressure drop and adjust the flow rate to selected assemblies is particularly useful in adjusting the hydraulic stability of a core which contains two or more nuclear fuel designs which have different intrinsic pressure drops (flow coefficients). While the foregoing description and drawings represent the preferred embodiments of the present invention, it will be apparent to those skilled in the art that various changes and modifications may be made therein without departing from the true spirit and scope of the present invention.