Patent Number: 046648828
Section: claims

1. A continuous segmented fuel and moderator rod for use with a water cooled and moderated nuclear fuel assembly, said rod comprising: (a) a lower fuel region containing a column of nuclear fuel;  (b) a moderator region, disposed axially above the fuel region, said moderator region having means for admitting and passing said water moderator therethrough for moderating an upper portion of the nuclear fuel assembly, said moderator region being separated from said fuel region by a water tight separator.  (a) a fuel bundle including a plurality of elongate nuclear fuel rods held in a spaced lateral array, each of said fuel rods being positioned in one of a plurality of predetermined lattice positions defined by an upper and a lower tie plate;  (b) a flow channel for enclosing said fuel bundle;  (c) a base member, secured to said flow channel and having means for supporting said fuel bundle within said flow channel, said base member further including nozzle for admitting moderator/coolant into said fuel assembly;  (d) at least one continuous segmented fuel and moderator rod disposed in said fuel bundle in one of said fuel rod lattice positions, said segmented rod including a lower fuel region containing a column of nuclear fuel and an upper moderator region separated from said lower fuel region by a water tight seal, said moderator region having an aperture means for passing said moderator/coolent into and through said moderator region for improving an H/U ratio of an upper portion of said fuel assembly.  (a) passing moderator/coolant through a fuel bundle of said fuel assembly;  (b) providing at least one continuous, fuel and moderator rod having an upper moderator region and a lower fuel region;  (c) passing a portion of said moderator/coolant through said moderator region of the segmented rod while maintaining said moderator at a substantially constant void fraction in the range of between 0-20% to thereby improve the H/U ratio at said upper portion of the fuel assembly. 2. The segmented rod of claim 1 further comprising a cladding for containing said lower fuel region and said moderator region, and said lower fuel region further containing a fission gas plenum region disposed between said column of neclear fuel and said moderator region. 3. The segmented rod of claim 2 wherein said separator comprises a disk-shaped separator affixed to said cladding to separate said moderator region from said fuel region. 4. The segmented rod of claim 2 wherein said means for admitting and passing comprises at least one inlet hole in the cladding of said moderator region. 5. The segmented rod of claim 4 wherein said means for admitting and passing further comprises at least one outlet hole in said cladding near the top of said moderator region for passing flowing moderator out of said moderator region. 6. The segmented rod of claim 4 wherein said moderator comprises subcooled water and said at least one inlet hole in sized and positioned to admit subcooled water having a void fraction of between about 0-20%. 7. The segmented rod of claim 5 wherein said at least one outlet hole is positioned to discharge moderator into a region of said nuclear fuel assembly where the void fraction is between about 20-70%. 8. A nuclear fuel assembly for a boiling water reactor (BWR) core comprising: 9. The nuclear fuel assembly for claim 8 wherein said segmented rod further comprises a cladding for containing said column of nuclear fuel and said moderator region and an upper end plug for mating an upper end of said segmented rod with said upper tie plate and a lower end plug for sealing the bottom of said cladding and for mating a lower end of said segmented rod with said lower tie plate. 10. The nuclear fuel assembly of claim 8 wherein said segmented rod further comprises a fission gas plenum region disposed between said column of nuclear fuel and said moderator region and separated from said moderator region by said water tight seal. 11. The nuclear fuel assembly of claim 10 wherein said water tight seal comprises a disk welded to said cladding and wherein said aperture means comprises at least one inlet flow aperture disposed above said disk. 12. The nuclear fuel assembly for claim 11 wherein said at least one inlet flow aperture is axially located within said fuel assembly at a position where a void fraction of the coolant is between about 0-20%. 13. The nuclear fuel assembly of claim 11 wherein said aperture means further comprises at least one flow outlet aperture for passing moderator out of said moderator region of said segmented rod. 14. A method of moderating a normally undermoderate upper portion of a boiling water reactor (BWR) fuel assembly comprising the steps of: