Patent Number: 046506373
Section: claims

1. A method of locating a defective fuel rod within a nuclear fuel assembly that is leaking radioactive products into surrounding coolant of a liquid coolant bath in which said fuel assembly is immersed, wherein said fuel rod is one of a plurality of fuel rods interconnected in a generally parallel spaced-apart matrix in the fuel assembly, said method comprising the steps of: (a) physically isolating successive longitudinal segments of said matrix of fuel rods from adjacent portions of said coolant bath at least along two opposing lateral sides of said matrix;  (b) selectively sampling the coolant surrounding said plurality of fuel rods within each of said successive physically isolated longitudinal segments of said matrix to determine the approximate one of said successive longitudinal segments at which radioactive products are being emitted from a fuel rod therein;  (c) physically isolating successive submatrices of fuel rods at least along two opposing lateral sides of each of said submatrices from adjacent fuel rods in said approximate one of said successive longitudinal segments of said matrix at which it was determined that radioactive products were being emitted from a fuel rod therein; and  (d) selectively sampling the coolant surrounding said fuel rods within each of said successive physically isolated submatrices to determine the one of said successive submatrices at which radioactive products are being emitted from a fuel rod therein.  (a) drawing a sample of said coolant from a volumetric test zone defined respectively by each of said physically isolated longitudinal segments of said matrix of fuel rods and each of said physically isolated submatrices of said approximate one of said longitudinal segments of said matrix of fuel rods; and  (b) measuring the radioactive product content of said drawn sample.  (a) placing a coolant sample probe of the type having a pair of baffles extending in cantilevered manner from a collector member to free ends and defining therebetween a volumetric test zone, in cooperative proximity to said fuel assembly rods and intermediate said first and second ends thereof such that a longitudinal segment of at least one of said fuel rods is disposed within said volumetric test zone and physically isolated by said baffles from any fuel rods in said assembly being located outside of said test zone; and  (b) sampling the radioactive content of liquid coolant of said volumetric test zone when said sample probe is positioned as in step (a).  (a) a pair of opposed baffles longitudinally extending between first and second ends;  (b) a collector operatively connecting said baffles adjacent said first ends thereof so as to define a volumetric test zone between said opposed baffles; said collector being configured to collect liquid coolant drawn from said volumetric test zone; and  (c) wherein said probe apparatus is configured for operative alignment with a nuclear fuel rod assembly such that said baffles laterally project on opposite sides of at least one fuel rod of said assembly so as to encompass a longitudinal segment of said fuel rod within said volumetric test zone and physically isolate said longitudinal segment of said fuel rod within said test zone from any fuel rods in said assembly being located outside of said test zone.  (a) determining the approximate one of a succession of longitudinal segments of said matrix of fuel rods at which radioactive products are being emitted from a fuel rod of said matrix;  (b) physically isolating successive submatrices of fuel rods at least along two opposing lateral sides of each of said submatrices from adjacent fuel rods in said approximate one longitudinal segment of said matrix at which it was determined that radioactive products were being emitted from a fuel rod therein; and  (c) selectively sampling the coolant surrounding said fuel rods within each of said successive physically isolated submatrices to determine the one of said successive submatrices at which radioactive products are being emitted from a fuel rod therein.  (a) drawing a sample of said coolant from said volumetric test zone defined respectively by each of said physically isolated submatrices of said matrix of fuel rods; and  (b) measuring the radioactive product content of said drawn sample. 2. The method as recited in claim 1, wherein the approximate one of the longitudinal segments of said matrix of fuel rods in said fuel assembly containing the leaking fuel rod is the longitudinal segment which contains the coolant with the highest sampled radioactive product content. 3. The method as recited in claim 1, wherein said step of physically isolating successive longitudinal segments of said matrix of fuel rods comprises defining a volumetric test zone about each one of said successive longitudinal segments wherein said volumetric test zone in one direction circumferentially encompasses the fuel rods in said matrix thereof in a plane transverse to the longitudinal axes of the fuel rods and in another direction longitudinally extends in the axial direction of said fuel rods a distance substantially less than the length of said fuel rods. 4. The method as recited in claim 1, wherein said each sampling step comprises: 5. The method as recited in claim 1, wherein the sampling for said radioactive products of coolant surrounding said fuel rods within said submatrices is carried out in logical manner so as to isolate that fuel rod that is emitting said radioactive products into its surrounding coolant. 6. The method as recited in claim 1, wherein said step of physically isolating successive submatrices of fuel rods comprises selectively inserting one or more baffle members between adjacent rows of said fuel rods within said matrix thereof so as to isolate the coolant surrounding said fuel rods within one submatrix from that of an adjacent submatrix. 7. The method as recited in claim 6, wherein said baffle members are inserted between said adjacent fuel rod rows in a direction transverse to the longitudinal axes of said fuel rods. 8. A method of locating a leaking fuel rod in a nuclear fuel rod assembly of the type having a plurality of elongate fuel rods longitudinally extending between first and second ends in generally parallel spaced-apart manner and disposed within a liquid coolant bath, comprising the steps of: 9. The method as recited in claim 8, wherein said fuel rod assembly has a cross-sectional area defining a matrix of a plurality of said fuel rods, and wherein said coolant sample probe is sized and configured and is placed in cooperative proximity with said fuel rod assembly such that longitudinal segments of substantially the entire matrix of said plurality of fuel rods are disposed within said volumetric test zone. 10. The method as recited in claim 9, wherein said baffles are characterized by an effective length dimension extending from said collector member toward said free ends and an effective width dimension generally orthogonally disposed to said length dimension and substantially less than the length of said fuel rods as measured between said first and said second ends thereof; wherein said baffles are disposed such that their width dimension lies generally parallel with the longitudinal axes of said fuel rods when said coolant sample probe is operatively positioned in close proximity to said fuel assembly rods. 11. The method as recited in claim 10, including the step of longitudinally moving said coolant sample probe relative to said fuel rod assembly such that said volumetric test zone traverses and said sampling is performed over substantially the entire length of said fuel rods between said first and said second ends thereof. 12. The method as recited in claim 11, including the step of determining that longitudinal position of said coolant sample probe relative to said fuel assembly where said radioactive content of said liquid coolant sample from said volumetric test zone is a maximum. 13. The method as recited in claim 8, wherein the step of placing said coolant sample probe in cooperative proximity to said fuel assembly rods comprises the step of moving said probe member relative to said fuel rod assembly such that at least one of said baffle members cooperatively slides between adjacent rows of said fuel rods, thereby isolating the longitudinal segments of those fuel rods within said volumetric test zone from those fuel rods outside of said test zone. 14. The method as recited in claim 13, including the step of systematically moving said test probe relative to said fuel rod assembly so as to isolate longitudinal segments of different groups of said fuel rods, and performing said sampling step on each of said groups of said fuel rods. 15. The method as recited in claim 14, wherein said fuel rod assembly has a cross-sectional area defining a matrix of a plurality of said fuel rods, and wherein said coolant sample probe is sized and configured to encompass approximately one-half of said fuel rods of said matrix within said volumetric test zone. 16. The method as recited in claim 15, further including the step of systematically moving said test probe and performing said sampling so as to subdivide said matrix of fuel rods into test quadrants. 17. The method as recited in claim 8, wherein the step of sampling includes drawing a sample of liquid coolant from said volumetric test zone and testing the radioactive content of said drawn coolant sample. 18. Test probe apparatus for determining the position of leaking fuel rods in a nuclear fuel rod assembly of the type having a plurality of elongate spaced fuel rods interconnected in generally parallel configuration, comprising: 19. Test probe apparatus as recited in claim 18, further including means cooperatively connected with said collector for drawing liquid coolant from said volumetric test zone through said collector. 20. Test probe apparatus as recited in claim 19, further including sensor means operatively connected with said collector for measuring the radioactive content of said liquid coolant drawn through said collector. 21. Test probe apparatus as recited in claim 18, further including means operatively connected with said baffles and collector for moving said volumetric test zone longitudinally relative to said fuel assembly rods. 22. Test probe apparatus as recited in claim 18, further including means operatively connected with said baffles and collector for moving said volumetric test zone laterally relative to said fuel assembly, whereby the number of said longitudinal segments of said fuel rods contained within said volumetric test zone at any instant of time can be selectively varied. 23. Test probe apparatus as recited in claim 22, further including means operatively connected with said baffles and collector for moving said volumetric test zone longitudinally relative to said fuel assembly rods. 24. Test probe apparatus as recited in claim 18, wherein said baffles are constructed of thin, semirigid sheet material having a thickness less than 0.20 inches. 25. Test probe apparatus as recited in claim 18, wherein said baffles are generally planar, and are disposed parallel to one another, and wherein at least one of said baffles is constructed of thin sheet material having a thickness sized to cooperatively slide between adjacent ones of said fuel rods within said fuel assembly. 26. Test probe apparatus as recited in claim 25, wherein said baffles are constructed of thin, semirigid sheet material having a thickness less than 0.20 inches. 27. Test probe apparatus as recited in claim 18, wherein said baffles are constructed of thin, semirigid sheet material having a thickness less than 0.10 inches. 28. Test probe apparatus as recited in claim 18, wherein the fuel assembly with which the probe is to be used has a cross-sectional area dimension as measured in a plane generally perpendicular to the longitudinal axes of said fuel rods and a longitudinal length dimension generally equal to that of the plurality of fuel rods comprising said fuel assembly; wherein said baffles are disposed generally parallel to one another; wherein said volumetric test zone has a cross-sectional area dimension as measured in a plane perpendicular to said baffles and extending through said collector which is larger than said fuel assembly cross-sectional area; and wherein the height of said baffles as measured perpendicular to the volumetric test zone cross-sectional dimension is significantly less than the longitudinal length of said fuel assembly. 29. Test probe apparatus as recited in claim 18, wherein the fuel assembly with which the probe is to be used has a cross-sectional area dimension as measured in a plane generally perpendicular to the longitudinal axes of said fuel rods and a longitudinal length dimension generally equal to that of the plurality of fuel rods comprising said fuel assembly; wherein said baffles are disposed generally parallel to one another; wherein said volumetric test zone has a cross-sectional area dimension as measured in a plane perpendicular to said baffles and extending through said collector which is approximately one-half that of said fuel assembly cross-sectional area; and wherein the height of said baffles as measured perpendicular to the volumetric test zone cross-sectinal dimension is significantly less than the longitudinal length of said fuel assembly. 30. A method of locating a defective fuel rod within a nuclear fuel assembly that is leaking radioactive products into surrounding coolant of a liquid coolant bath in which said fuel assembly is immersed, wherein said fuel rod is one of a plurality of fuel rods interconnected in a generally parallel spaced-apart matrix in the fuel assembly, said method comprising the steps of: 31. The method as recited in claim 30 wherein said step of physically isolating successive submatrices of said approximate one longitudinal segment of said matrix of fuel rods comprises defining a volumetric test zone about each one of said successive submatrices wherein said volumetric test zone in one direction circumferentially encompasses the fuel rods in said submatrix thereof in a plane transverse to the longitudinal axes of the fuel rods and in another direction longitudinally extends in the axial direction of said fuel rods a distance substantially less than the length of said fuel rods. 32. The method as recited in claim 31, wherein said each sampling step comprises: 33. The method as recited in claim 30, wherein the sampling for said radioactive products of coolant surrounding said fuel rods within said submatrices is carried out in logical manner so as to isolate that fuel rod that is emitting said radioactive products into its surrounding coolant. 34. The method as recited in claim 30, wherein said step of physically isolating successive submatrices of fuel rods comprises selectively inserting one or more baffle members between adjacent rows of said fuel rods within said matrix thereof so as to isolate the coolant surrounding said fuel rods within one submatrix from that of an adjacent submatrix.