Abstract:
A tool for delivery of a testing element to a limited access location within a nuclear containment includes a rotation apparatus having a connection element that is configured to have an aperture that is formed generally centrally therein. A submersible machine is structured to carry the tool to a limited access location within a nuclear containment. The submersible machine includes a mount apparatus configured to be movably clamped onto a steam dam of a nuclear reactor apparatus and to drive the submersible machine circumferentially along the steam dam to inspect a plurality of jet pumps or other limited access locations of the nuclear reactor apparatus. The improved submersible machine advantageously further includes an adjustment table between the mount apparatus and a frame that carries the tool to enable rapid accurate positioning of the frame, and thus the tool, once the submersible machine has been mounted to the steam dam.
Abstract:
A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement.
Abstract:
Disclosed is an apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, which removes an unintentionally separated thermal sleeve without pipe cutting, preventing invasion of impurities into pipes and achieving reliable pipe re-welding. The apparatus includes a sleeve removal tool including a corn head formed at a shaft, a pressure plate below the corn head to maximize hydraulic pressure inside a safety injection pipe, a spring connected to the pressure plate to keep the pressure plate unfolded, and a guide wheel to guide the sleeve removal tool into the safety injection pipe, a horizontal movement carrier including bodies connected to each other by a link, a seating rod for seating of the sleeve removal tool, and moving wheels for movement of the horizontal movement carrier, and a vertical movement carrier including first and second anti-separation bars to prevent separation of the horizontal movement carrier.
Abstract:
In various embodiments, the system includes a tubular female end portion of the first pole section and a male end portion of the second pole section that is insertable into the female end portion. The system additionally includes a locking nut threadingly engaged with the male end portion that is rotatable on the male end portion to longitudinally transition the locking nut into contact with the female end portion to fixedly interlock the male and female end portions. Furthermore, the system includes a biased locking sleeve assembly slidably and rotatably mounted on a locking assembly portion of the second pole. The locking sleeve assembly can include a locking sleeve and a biased plunger slidingly positioned within an interior of the locking sleeve for applying a locking force to the locking nut.
Abstract:
A telescoping mast with zero clearance which can be used in a fully automatic, relative positioning refueling machine. The telescoping mast consists of a series of nested tubes separated by spacers of unique design. Each spacer consists of an upper spacer assembly attached to the upper end of an inner tube segment nested in an outer tube segment and slidable inside the outer tube segment; and a lower spacer assembly attached to the lower end of the outer tube segment and slidable outside the inner tube segment. The spacer assemblies are preferably made of molded plastic, for example, polyethylene. Each spacer assembly is formed by a spacer ring and a plurality of corrugated members connected at one end to the spacer ring. The distal ends of the corrugated members of the upper spacer assembly contact the distal ends of respective ones of the corrugated members of the lower spacer assembly when the inner tube segment is in an extended position relative to the outer tube segment. Each of the corrugated members comprises a multiplicity of spacer blocks connected in series by a multiplicity of flexible beams. Bending of the flexible beams during compression of the spacer assemblies provides damping of the force produced upon impact when the inner tube segment drops relative to the outer tube segment, for instance, after the inner tube segment has been stuck and then slips relative to the outer tube segment.
Abstract:
A hollow tubular guiding mast made up of interconnected axial sections and adapted for reciprocably guiding the gripper or charging body for a core reactor. The mast includes reinforcing spars extending axially therein in the form of interconnected flat plates which diverge in the outward direction of the mast. Guide means, such as rollers, are adjustably mounted on the plates and engage angularly related regions of the body to be guided in the mast.
Abstract:
A gripping and lifting device, especially for use with fuel elements and control rod means in a nuclear core reactor in which a carriage having a winch thereon supports a mast beneath the carriage in which is slidable a tubular body within which, in turn, is slidable a housing. Cables lead from the winch to the first body for vertical movement thereof while the housing has limited axial movement in the aforementioned body. On the lower end of the housing are two gripper devices, one for engagement with the control rods and the other for engagement with the fuel element. Separate actuators are provided for the two grippers and sensing devices are included in the structure for sensing the positions of the grippers. A feature of the arrangement is that when the body is elevated and the housing moves downwardly therein to a stopped position, the gripper for the fuel element is locked in its respective position.
Abstract:
In a nuclear reactor of the boiling light water type the steamwater mixture produced in the fuel cartridges is passed through steam-water separators in which the steam is separated from the water. According to an improved embodiment a fuel cartridge is united with a steam-water separator to form a unit. Said unit can be lifted by a refueling machine, so as to be inserted into and removed from the reactor through a refueling tube.
Abstract:
A T-COUPLING IS PROVIDED BETWEEN THE FUEL STRING AND THE CLOSURE PLUG ASSEMBLY TOGETHER FORMING A FUEL AGGREGATE FOR LOADING INTO EACH REACTOR FUEL CHANNEL. A FUELLING MACHINE COMPRISES A MINIMUM OF TWO BARRELS, ONE FOR RECEIVING THE FUEL STRING AND ONE FOR RECEIVING THE PLUG ASSEMBLY, THE BARRELS BEING DISPOSED IN A TURRENT ROTATABLE ABOUT AN AXIS PARRALLEL TO THE BARRELS AND THE FUEL CHANNEL. INTERMEDIATE ENGAGEMENT OR DISENGAGEMENT OF THE COUPING WHEN LOADING OR UNLOADING A FUEL CHANNEL IS MADE BY ROTATING THE TURRET.