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 syringe plunger position detection and alarm system continuously determines the position of a syringe plunger and provides near end of travel and end of travel alarms. Plunger movement is also monitored and if movement is less than a calculated amount, an alarm is provided. A variety of syringes of different sizes is usable. A potentiometer is mounted along the line of travel of the screw drive mechanism and a marker is mounted to extend from the screw mechanism to the potentiometer to force an internal contact in the potentiometer. The voltage provided by this internal contact is analyzed by the process to derive absolute and relative position of the plunger. The end of travel position of each plunger is stored in processor memory and from the operator input rate of infusion, the characteristic curve of the potentiometer also stored in memory, the plunger displacement of the syringe, and the time of the near end of travel alarm, the voltage of the near end of travel position is calculated.

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 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 heat exchange apparatus for transferring heat from a reactor gas coolant to a secondary fluid medium. The heat exchange apparatus comprises an elongated vertically extending hole in a concrete shield. Supported within the hole in spaced relation to the wall thereof is an elongated vertical extending tubular shroud which shroud has a gas entry at its lower end and a gas exit at its upper end. Means are provided for dividing the annular space between the shroud 16 and the wall of the hole into an upper and a lower region. Disposed in the shield is an inlet for reactor coolant which communicates with the lower region and is positioned vertically so as to be spaced above the gas entry to the shroud to thereby suppress natural convection during non-operating standby conditions of the apparatus. An outlet for reactor coolant, which is disposed in the shield, communicates with the upper region.