Abstract: A grid crusher apparatus and method are provided for a nuclear fuel rod consolidation system. Spacer grids are crushed within a basket which is then placed in a storage canister. The grid crusher apparatus has a ram assembly and a basket driving mechanism. The ram assembly has a sleeve ram and a central ram. The sleeve ram surrounds the central ram which is longitudinally movable within the sleeve ram. The central ram protrudes from the sleeve ram at a ram contact end and is retractable upon application of a preselected force to the central ram so that the central ram is flush with the sleeve ram at the ram contact end. The basket driving mechanism is configured to move the basket containing a spacer grid towards the ram contact end so that the spacer grid is crushed within the basket. The spacer grid is crushed by the combination of successive forces from the central ram and the sleeve ram, respectively.

Abstract: A storage canister for spent nuclear fuel rods, having loading and storage configurations, has an open end and an apertured end wall, and means therein defining a plurality of rod locations. The canister also has movable means therein for vertically offsetting adjacent rods within the canister so that any pair of adjacent rods are vertically offset from each other. The movable means is positioned during loading to permit fluid flow into and out of the canister through the apertured end wall and in the storage configuration blocks at least one of the apertures in the end wall. The movable means may also be used to lift the fuel rods such that their tops extend above the canister body to permit removal of one or more rods. A closure member for the open end has a locking mechanism for locking it to the canister and a tamper indicating mechanism.

Abstract: A tool guide plate for use in a rod consolidation system for the consolidation of spent fuel rods within a storage container. The system utilizes a robot in conjunction with long reach tools to remove spent fuel rods from an array of rods in a rod assembly and to transfer them to a rod consolidation holder. The tool guide plate has a plurality of apertures shaped to receive the end of a tool and less than the number of rods in the array and has means located on the guide plate for indexing the apertures over the rod position to provide tool access to all of the rods in the array, the apertures providing access to a plurality of rod positions in each index position.

Abstract: An apparatus for the consolidation of spent nuclear fuel rods within a storage pool uses a robot in conjunction with long reach tools to remove spent fuel rods from a rod assembly and transfer them to a fuel rod consolidation canister. A movable curtain within the canister aligns and locates the rods for most efficient use of space. A tool guide plate enables the long reach rod grasping tool to locate each rod in the fuel cell accurately.

Abstract: A spent nuclear fuel shipping basket and cask assembly has a basket made of a plurality of apertured metal disks maintained in spaced array and axial alignment. The basket has end caps which hold fuel assembly containing sleeves while permitting the fuel assembly to pass partially through the end caps and abut the end walls of the cask.

Abstract: A closure arrangement for spent nuclear fuel shipping container has a lid member with a peripheral groove in its outer edge, the lid member being adapted to rests upon a shoulder within a bore at the mouth of the cask. The lid is forced into sealing engagement with the shoulder by a plurality of radially disposed wedges extending from the inner wall of the cask into the peripheral groove. The wedges are moved by bolts extending through the wall of the cask and cam the lid down against the shoulder as they are forced into the groove.

Abstract: A spent nuclear fuel shipping basket has a plurality of tubes of corrosion resistant material, each tube being adapted to contain a spent nuclear fuel rod assembly. The tubes are arranged in a geometric pattern within a circular cask, and are totally independent of each other, with neutron poisoning material between adjacent tubes. Filler blocks of heat absorbing material which may also contain neutron poisoning material are inserted into the empty spaces between the tubes and the wall of the cask, and are independent of both tubes and wall.