Shroud repair apparatus

This invention relates generally to maintenance and repair of nuclear reactors, and more particularly, to the repair of the fuel core shroud of a boiling water nuclear reactor. A repair apparatus for a shroud in a nuclear reactor pressure vessel is described. The repair apparatus includes an upper stabilizer assembly, a lower stabilizer assembly, and a tie rod configured to extend between and to couple to the upper and lower stabilizer assemblies. The upper stabilizer includes a stabilizer block and an upper stabilizer wedge slidably coupled to the upper stabilizer block. The upper stabilizer block is configured to couple to a shroud lug. The upper stabilizer wedge includes an integral leaf spring portion formed by a slot in the wedge and is configured to engage the side wall of the reactor pressure vessel. The lower stabilizer assembly includes a stabilizer block and a lower stabilizer wedge slidably coupled to the lower stabilizer block. The lower stabilizer block is configured to engage the shroud. A horizontal stabilizing spring is attached to the wedge and is configured to engage the side wall of the reactor pressure vessel. The tie rod is threaded at each end. One end threadedly engages a tie rod opening in the bottom stabilizer block. The other end is received by the upper stabilizer block and is secured by a tie rod nut.