Patent Number: 052271285
Section: claims

1. A fuel assembly removably positionable in a reactor core inside a pressure vessel of a nuclear reactor comprising: an upper tie plate;  a lower tie plate spaced from said upper tie plate, and including a lower manifold therein;  a plurality of laterally spaced apart fuel rods extending longitudinally between said upper and lower tie plates and joined thereto;  a plurality of laterally spaced apart hollow control rods extending longitudinally between said upper and lower tie plates and joined in flow communication with said lower manifold;  a reservoir containing a neutron absorbing control liquid joined to said lower tie plate in flow communication with said lower manifold, and being removable together with said fuel assembly when said fuel assembly is removed from said reactor core; and  means for pumping said control liquid from said reservoir through said lower manifold and into said control rods for selectively varying the level of said control liquid in said control rods.  a lower housing fixedly joined to said lower tie plate and surrounding said reservoir, and including a lower nosepiece for channeling a liquid coolant into said lower housing and around said reservoir; and  wherein said lower tie plate includes a plurality of inlets extending therethrough at respective ones of said fuel rods, and disposed in flow communication with said lower housing for channeling said coolant through said lower tie plate and along said fuel rods.  a lower bellows disposed inside said reservoir in flow communication with said lower manifold, said lower bellows containing said control liquid; and  wherein said pumping means include a piston disposed inside said reservoir and adjacent to said lower bellows, said piston being selectively translatable inside said reservoir for selectively compressing said lower bellows to pump said control liquid into said lower manifold and said control rods for varying said control liquid level.  said reservoir is spaced longitudinally from said lower tie plate to define an access channel for allowing said coolant to flow from said metering orifice around said reservoir and into said lower tie plate inlets; and  further comprising a transfer tube extending between said lower tie plate and said reservoir and disposed in flow communication between said lower manifold and said lower bellows for channeling said control liquid therebetween.  an actuator having a selectively extendable plunger positionable through said lower nosepiece and into said reservoir for translating said piston to selectively compress said lower bellows to pump said control liquid into said control rods to raise said level thereof. 2. A fuel assembly according to claim 1 further comprising: 3. A fuel assembly according to claim 2 further comprising: 4. A fuel assembly according to claim 3 wherein said reservoir is spaced radially inwardly from said lower housing to define an annular orifice for metering flow of said coolant through said lower tie plate inlets. 5. A fuel assembly according to claim 4 wherein: 6. A fuel assembly according to claim 5 being top-and-bottom symmetrical for being reversible in said reactor core and including an upper manifold in said upper tie plate in flow communication with said control rods, and an upper bellows in flow communication with said upper manifold. 7. A fuel assembly according to claim 6 wherein said control rods include a non-neutron absorbing fluid being displacable from said control rods as said control liquid is pumped therein. 8. A fuel assembly according to claim 7 wherein said displacable fluid is a liquid being immiscible with said control liquid and effective for moderating neutrons emitted from said fuel rods, said upper bellows being effective for storing said liquid moderator upon displacement thereof from said control rods by said control liquid pumped therein. 9. A fuel assembly according to claim 6 wherein said pumping means further include: 10. A fuel assembly according to claim 9 wherein said actuator is disposed inside said reactor pressure vessel below said reactor core.