Abstract An illustrative embodiment of the invention discloses a technique for disassembling a nuclear reactor fuel element without destroying the individual fuel pins and other structural components from which the element is assembled. A traveling bridge and trolley that span a water-filled spent fuel storage pool support a strongback. The strongback is under water and provides a working surface on which the spent fuel element is placed for inspection and for the manipulation that is associated with disassembly and assembly. To remove, in a non-destructive manner, the grids that hold the fuel pins in the proper relative positions within the element, bars are inserted through apertures in the grids with the aid of special tools. These bars are rotated to flex the adjacent grid walls and, in this way relax the physical engagement between protruding portions of the grid walls and the associated fuel pins. With the grid structure so flexed to relax the physical grip on the indiviudal fuel pins, these pins can be withdrawn for inspection or replacement as necessary without imposing a need to destroy fuel element components.
Apparatus for manipulating a nuclear fuel element that is submerged in a pool comprising, a bridge spanning the pool and movable therealong, depending members extending from said bridge into the pool and movable on said bridge structure, said depending members being substantially inflexible with a constant separation therebetween, a strongback having a first and second end, said strongback being submerged in the pool and selectively positioned between said depending members, said strongback selectively pivotal about either of its ends, said strongback spanning the separation between said depending members, a pin extending from at least one of said depending members through a pivotal connection on the first end of the said strongback to enable said strongback to pivot through approximately 90° from a direction that is generally between said depending members and parallel to said bridge into a direction that is essentially perpendicular to said bridge and parallel to said depending members in order to engage and support the nuclear reactor fuel element thereon.
Claim 2
Dependent Claim
163 words
Apparatus for manipulating a nuclear fuel element that is submerged in a pool comprising, a bridge spanning the pool and movable therealong, depending members extending from said bridge into the pool and movable on said bridge structure, said depending members being substantially inflexible with a constant separation therebetween, a strongback having a first and second end, said strongback being submerged in the pool and selectively positioned between said depending members, said strongback selectively pivotal about either of its ends, said strongback spanning the separation between said depending members, a pin extending from at least one of said depending members through a pivotal connection on the first end of the said strongback to enable said strongback to pivot through approximately 90° from a direction that is generally between said depending members and parallel to said bridge into a direction that is essentially perpendicular to said bridge and parallel to said depending members in order to engage and support the nuclear reactor fuel element thereon.
Claim 3
Dependent Claim
38 words
Apparatus according to claim 1 further comprising a winch on said bridge and a cable connecting said winch with the second end of said strongback for selectively enabling said strongback to pivot into said perpendicular and parallel directions.
Claim 4
Dependent Claim
25 words
Apparatus according to claim 2 further comprising a trolley on said bridge and movable therealong to advance the manipulation of the nuclear reactor fuel element.