Abstract: Removable cruciforms are selectively installed at predetermined, spaced elevations within ice baskets associated with a nuclear power system, each ice basket having a generally cylindrical sidewall with plural, annular retaining rings secured therein at predetermined, spaced elevations, each cruciform being installed at predetermined, axially displaced elevations, engaging a corresponding annular retaining ring. Each cruciform comprises a pair of brackets joined together between parallel base portions by respective support plate assemblies and slide plates in telescoping, sliding relationshp, defining with the base portions, a spring housing of generally square configuration within which a generally C-shaped spring is received. A pair of legs extends integrally from the longitudinal edges of the base portion of each bracket, angularly disposed so as to extend radially within the ice basket.

Abstract: A handling tool for selectively removable cruciforms employed in ice baskets of the type employed with nuclear power generator systems. The tool includes clamping means for engaging a compressible central portion of the removable cruciform to retract same inwardly and permit moving same, in a horizontal orientation, throughout the axial height of the interior of the ice basket. When at a desired elevation, selective actuating means moves previously retracted guide means to an extended or projected position for engaging a retaining ring of the ice basket and supporting the tool on the ring. The clamping means is selectively actuated to the disengaged position for releasing the cruciform whereupon the same expands, projecting legs associated therewith radially outwardly and engaging the retaining ring, to support the cruciform on the ring. The tool may thereafter be removed.

Abstract: A weighing tool and method for determining the weight of ice contained within each of a plurality of ice baskets received within corresponding compartments of a lattice frame, as employed with nuclear power generators. A cylinder body includes lug support frames and corresponding lugs movable to retracted positions for inserting the weighing tool within the upper end of an ice basket, and to extended positions for being engaging in the ice basket and securing the tool thereto. A piston movable in sliding relationship within the body and defining upper and lower compartment therein is secured through a piston rod to a support bar which rests on the lattice frame and spans the compartment. Hydraulic fluid under controlled, increasing pressure is introduced into the upper compartment, driving the cylinder body upwardly relatively to the stationary piston so as to raise the ice basket. The pressure necessary to lift the ice basket provides a measure of the total weight of the ice basket.

Abstract: The spent fuel consolidation system provides a system for vertically and remotely dismantling an irradiated nuclear fuel assembly while the fuel assembly remains submerged in a coolant and for consolidating the spent fuel rods of the dismantled fuel assembly. The system comprises a platform rotatably mounted on a vertical support with a fuel assembly station, a consolidation station, and a canister station attached to the platform. A gripper mechanism is slidably disposed on the vertical support for transferring spent fuel rods from one station to another as the various stations are rotated into alignment with the gripper mechanism. The fuel assembly station provides a station for holding the fuel assembly while the spent fuel rods are removed therefrom, the consolidation station provides a station for consolidating the spent fuel rods, and the canister station provides a station for holding the consolidated spent fuel rods.