Westinghouse Electric Company LLC

Westinghouse Electric Corporation

Louis J Tylman

David John Stefko

Christopher Marc Burton

David A Howell

Thomas H Dent

Stephan L Abbott

A CRDS unlatching tool includes a support assembly and a latching assembly, wherein the support assembly is received within the latching assembly in a manner wherein the latching assembly is moveable relative to the support assembly. The support assembly has a plurality of latch fingers and at least one pin, each of the latch fingers being movable between a latched position wherein the latch finger is structured to engage and hold the CRDS an unlatched position wherein the latch finger is structured to not engage the CRDS. The latching assembly includes a first sleeve member and a second sleeve member, the second sleeve member having at least one slot, wherein the at least one pin is moveably received within the at least one slot. The latching assembly is movable from a latched state to an unlatched state wherein the latch fingers are actuated by the first sleeve member.

Control rod drive shaft unlatching tool

A pressure vessel having a removable closure head in a high radiation environment is closed by placing the closure head having a flange over and spaced from the flange of a pressure vessel body containing fissile material. The closure studs are installed in closure stud holes of the pressure vessel body flange. Transition nut members of hydraulic nut assemblies are threaded onto the closure studs. Hydraulic hoses are connected between the hydraulic nut assemblies and a pressure source. The pressure source simultaneously pressurizes the hydraulic nut assemblies to simultaneously apply a uniform force to the closure studs sufficient to seat the spaced apart closure head flange on the pressure vessel body flange and to elongate the closure studs. The hydraulic nut assemblies are locked in place over the closure head flange while the force is applied to the closure studs and the closure studs are elongated. The hydraulic pressure on the hydraulic nut assemblies is released while the hydraulic nut assemblies are locked in place over the closure head flange and the closure studs are elongated. The hydraulic nut assemblies may remain connected with the hydraulic hoses after the pressure vessel has been returned to on-line operations and is generating thermal power. The hydraulic hoses connected with the hydraulic nut assemblies may be vented while generating thermal power in the pressure vessel.

Method of closing a pressure vessel

A transfer device for moving a poison rod assembly between fuel cells in a nuclear fuel storage facility coupleable to an overhead crane. The poison rod assembly has a plurality of poison rods disposed in rows. The device includes an elongated outer member, an inner member, and a gripper assembly supported by the inner member. The inner member is slidably disposed within the elongated outer member. The overhead crane is coupled to the inner member for sliding said inner member between an upper position and a lower position. An interlock assembly selectively couples the inner member and elongated outer member. Thus, moving the crane, which is coupled to the inner member either moves the inner member relative to the elongated outer member when the interlock is not engaged, or, moves both the inner member and the elongated outer member when the interlock is engaged.

Interlock assembly for burnable poison rod transfer device

A transfer device for moving a poison rod assembly between fuel cells in a nuclear fuel storage facility, where the poison rod assembly has a plurality of poison rods depending from a web. The transfer device includes a frame assembly, a poison rod assembly lifting assembly, which is moveable between an upper position and a lower position, a plurality of comb assemblies. The comb assemblies are slidably mounted on the frame so that the comb assemblies slide between an open position and a closed position as the lifting assembly moves from its lower position to its upper position.

Slidable comb assembly for burnable poison rod transfer device

A refueling system for a nuclear power plant utilizing a data network to provide for automatic control and enhanced monitoring of the entire fuel transfer process. The refueling system of this invention provides integrated control of the refueling machine within the containment building, the spent fuel handling machine within the fuel storage building, and the fuel transfer system between the buildings. The system provides supervisory control of the overall system operation via a remote control station, while at the same time, having the capability for local on-line control of each element of the system in the event of network failure. The system may automatically identify individual fuel assemblies with an optical scanner. An in-mast sipper connected to the network automatically tests for leaking fuel assemblies. A revised core load pattern and a revised sequence plan can be calculated by the system in the event of the discovery of a leaking fuel assembly. The system may also include a fuel loading guide to facilitate the automatic loading of bowed fuel assemblies. Human interface with the system may be provided at a plurality of locations, including for example, a refueling control station and a remote status panel. The reactivity of the reactor core may be monitored by the system during core loading, and corrective action taken automatically if a predetermined setpoint is exceeded. Core spacing verification may also be performed automatically.

Growing community of inventors

Acme, PA, United States of America

Louis J Tylman