摘要:
An improved system for repairing and reconstituting a fuel rod assembly in the spent fuel pool of a nuclear power plant is disclosed herein. The improved system includes a height-adjustable elevator and carriage assembly for lifting and inverting a pair a fuel assemblies with their bottom ends adjacent one another, a length-adjustable rod handling tool having a gripper for gripping, lifting, lowering and ungripping a fuel rod, and a dual-axis tool positioner mountable over the bottom ends of the inverted, adjacent fuel assemblies. The tool positioner includes a funnel-shaped tool guide that is movable over the bottom ends of the fuel assemblies for receiving and positioning the gripper of the rod handling tool. The improved system may be adjusted for use in spent fuel pools of substantially different dimensions and water levels without the need for additional parts, and may be operated by only two technicians.
摘要:
A spent nuclear fuel storage bridge comprising either a stationary or mobile structure supported from the walls of a spent nuclear fuel storage pool. The structure may have either a pivotally mounted or non-pivotally mounted lower basket or cage portion which occupies a region of the vertical space between the pool water surface and the existing pool floor supported fuel storage racks. Using the bridge, at least a ten-foot deep barrier of biological shield water and at least a two-foot space between the top of the existing racks and the bottom of the bridge can be maintained in a storage pool of typical geometrics and dimensions. By limiting the height of the basket portion of the bridge, up to a three-foot space beneath the biological shield water may be provided to accommodate underwater horizontal transference of spent fuel storage canisters to and from the bridge. The width of the basket portion is determined by the spent fuel length and the resulting storage canister length. Horizontally positioned fuel canisters are stacked vertically within a frame structure or thermal spacer assembly carried internally of the bridge for providing longitudinal and lateral support of the canisters and permitting cooling of the canisters. Also provided are novel fuel storage canister constructions and handling apparatus therefor.
摘要:
A storage apparatus for storing nuclear waste material. The storage apparatus is comprised of an elongated storage canister suitable for the positioning of nuclear waste material, such as spent fuel rods, therewithin. A canister cover covers one end of the storage canister, and may be maintained in an interlocking relationship with a storage canister. The canister cover may be quickly engaged with a remotely operated handling tool, and because of the interlocking engagement with the storage canister, the handling tool may be utilized to handle and reposition the entire storage canister.
摘要:
A system and a method for removing and consolidating the spent fuel rods of a fuel assembly is disclosed herein. The system comprises a pushing assembly having a push rod for pushing a selected fuel rod out of a fuel assembly, a fuel assembly positioner including an elevator for conveniently positioning a fuel assembly within the spent fuel pool of a nuclear facility, a rod catching grid for preventing the pushed-out fuel rods from falling to the bottom of the pool and a transition cannister for funneling the rods into a consolidated arrangement within a storage cannister. In operation, the push rod is positioned over and engaged against the upper end of a fuel rod to be removed from the assembly. Thus engaged, the push rod is inserted through the cells in the grids of the fuel assembly that surround the selected fuel rod, thereby pushing it out of the fuel assembly. Thus the grid cells are used as an alignment means for the push rod during the rod-pushing operation.
摘要:
A quick disconnect is provided to permit two cable ends to be rapidly connected and disconnected without the use of tools. The quick disconnect includes rear and front couplings which may be mounted to respective cable ends. Quick connection of the cable ends is effected by connecting the rear and front couplings to one another by a hinge latch. The hinge latch is retained in the closed position by a compression sleeve which surrounds the hinge latch. The front end of the compression sleeve includes a ring groove that retains a ring spring. The ring spring engages complementary retention grooves in the hinge latch to bias the hinge latch in the closed position, thus securing the front coupling to the rear coupling.
摘要:
A cask basket construction for storing and transporting nuclear waste material, such as spent nuclear fuel assemblies or fuel rods. The construction is comprised of a plurality of individual storage cells for storing the nuclear material, with the plurality of storage cells rigidly affixed to one another to form a high strength, lightweight, unitary array of storage cells. Thermal loading elements positioned between walls of adjacent ones of the cells as well as a coolant flow is provided to transfer heat generated by the nuclear material contained in the storage cells to the outer portions of the cask basket construction. A heat path is included for dissipating the heat transferred away from the center of the array of storage cells. The thermal loading elements further serve as an integral structural component of the array for enhancing the structural strength thereof.
摘要:
A system and a method for removing and consolidating the spent fuel rods of a fuel assembly is disclosed herein. The sytem comprises a pushing assembly having a push rod for pushing a selected fuel rod out of a fuel assembly, a fuel assembly positioner including an elevator for conveniently positioning a fuel assembly within the spent fuel pool of a nuclear facility, a rod catching grid for preventing the pushed-out fuel rods from falling to the bottom of the pool and a transition cannister for funneling the rods into a consolidated arrangement within a storage cannister. In operation, the push rod is positioned over and engaged against the upper end of a fuel rod to be removed from the assembly. Thus engaged, the push rod is inserted through the cells in the grids of the fuel assembly that surround the selected fuel rod, thereby pushing it out of the fuel assembly. Thus the grid cells are used as an alignment means for the push rod during the rod-pushing operation.