Patent Number: 047939630
Section: claims

1. In a nuclear reactor core having a multiplicity of fuel assemblies, a method of fuel interchange between said fuel assemblies, comprising the steps of: (a) inserting a cluster assembly of a first plurality thereof, with each cluster assembly of said first plurality containing an array of fuel rods having burnt fuel disposed therein, into a fuel assembly of a first plurality thereof, with each fuel assembly of said first plurality containing an array of fuel rods having fresh fuel disposed therein; and  (b) inserting a cluster assembly of a second plurality thereof, with each cluster assembly of said second plurality containing an array of fuel rods having fresh fuel disposed therein, into a fuel assembly of a second plurality thereof, with each fuel assembly of said second plurality containing an array of fuel rods having burnt fuel disposed therein;  (c) certain groups of said fuel rods in each fuel assembly being spaced apart laterally from one another by a greater distance than the rest of said fuel rods so as to define a plurality of empty elongated channels in an array being interspaced within said array of fuel rods, each elongated channel being in the form of an open space extending laterally between and longitudinally along said fuel rods of said certain groups thereof;  (d) said fuel rods of each cluster assembly in each of said first and second pluralities thereof being larger in size than said fuel rods of each fuel assembly in each of said first and second pluralities thereof, said larger size cluster assembly fuel rods being inserted in said elongated channels defined in said respective fuel asssemblies.  (a) first and second pluralities of said fuel assemblies, said fuel assembly in each plurality thereof having an array of elongated fuel rods therein , certain groups of said fuel rods in each fuel assembly being spaced apart laterally from one another by a greater distance than the rest of said fuel rods so as to define a plurality of empty elongated channels in an array being interspaced within said array of fuel rods, each elongated channel being in the form of an open space extending laterally between and longitudinally along said fuel rods of said certain groups thereof, said fuel rods in said first and second pluralities of fuel assemblies containing fresh and burnt fuel respectively; and  (b) first and second pluralities of cluster assemblies, said cluster assembly in each plurality thereof containing an array of elongated fuel rods being disposed in a pattern which matches that of said channels being interspaced within said array of fuel rods of each fuel assembly;  (c) said fuel rods of said first plurality of cluster assemblies containing burnt fuel therein and being removably inserted in a first group of said channels within said first plurality of fuel assemblies;  (d) said fuel rods of said second plurality of cluster assemblies containing fresh fuel therein and being removably inserted in a second group of said channels within said second plurality of fuel assemblies;  (e) said fuel rods of each cluster assembly in each of said first and second pluralities thereof being larger in size than said fuel rods of each fuel assembly in each of said first and second pluralities thereof. 2. The fuel interchange system as recited in claim 1, wherein said fuel rods of each cluster assembly are larger in diameter than said fuel rods of each fuel assembly. 3. The fuel interchange system as recited in claim 1, wherein said fuel rods of each cluster assembly are greater in length than said fuel rods of each fuel assembly. 4. In a nuclear reator core having a multiplicity of fuel assemblies, a system of fuel interchange between said fuel assemblies, comprising: 5. The fuel interchange system as recited in claim 4, wherein said fuel rods of each cluster assembly are larger in diameter than said fuel rods of each fuel assembly. 6. The fuel interchange system as recited in claim 4, wherein said fuel rods of each cluster assembly are greater in length than said fuel rods of each fuel assembly.