Abstract: Method and apparatus for surface conditioning a metal surface typically having irregular surface contours, by rubbing the metal surface with a surface conditioning device having a plurality of bristles which contact the metal surface during the rubbing and effect tensile stress reduction or degraded layer removal in the metal surface.

Abstract: A tool is disclosed for remotely inspecting and/or treating welds, pipes, vessels and/or other components used in reactor coolant systems or other process applications to, among other things, mitigate stress corrosion cracking in the welds, pipes, vessels and/or other components. The tool is placed at the entrance to a pipe or vessel and walks into the pipe or vessel to a pre-selected weld, pipe or vessel location or other component. Upon reaching the pre-selected weld, pipe or vessel location or other component, the tool anchors itself, then advances an end effector to inspect and/or treat the pre-selected weld, pipe or vessel location or other component.

Abstract: Method and apparatus for surface conditioning a metal surface typically having irregular surface contours, by rubbing the metal surface with a surface conditioning device having a plurality of bristles which contact the metal surface during the rubbing and effect tensile stress reduction or degraded layer removal in the metal surface.

Abstract: A lower housing having a lower chamber and a welding opening is fixed about an underwater weld site. The lower housing includes an upper opening, the lower housing being filled with water upon installation. A transport housing containing a welding unit in a dry state is lowered such that a bottom opening, closed by a closure element, registers with an upper opening of the lower chamber. Upon clamping the housings together, the lower chamber is at least partially evacuated. The closure element is then moved to an open position and the welding unit is lowered into the evacuated lower chamber to weld a patch to the vessel wall to overlay the damaged area.

Abstract: A system and method for inspecting, repairing and mitigating stress corrosion cracking on a pressure water reactor vessel. The reactor vessel includes inlet nozzles, outlet nozzles, and bottom mounted instrumentations. The method may include removing core barrels in the reactor vessel, installing a radiation shield in the reactor vessel, installing a coffer dam, draining the reactor vessel, lowering a tooling delivery robot into the reactor vessel, attaching the tooling delivery robot at a surface of the reactor vessel, lowering a tool cradle into the reactor vessel, and attaching the tool cradle at the surface of the reactor vessel.

Abstract: Method of joining a first metal to a surface of a second metal at a region susceptible to stress corrosion cracking, comprising applying an SCC-resistant Noble Metal weld Buttering or Noble Metal weld Cladding to said first metal prior adjacent to said region prior to welding said first metal to said surface of said second metal. Alternately, a method of applying Noble Metal Cladding over existing SCC susceptible weld deposits and/or heat affected zones. A metal component containing a Noble Metal weld Cladding or Buttering over existing SCC susceptible weld deposits and/or heat affected zones.

Abstract: A lower housing having a lower chamber and a welding opening is fixed about an underwater weld site. The lower housing includes an upper opening, the lower housing being filled with water upon installation. A transport housing containing a welding unit in a dry state is lowered such that a bottom opening, closed by a closure element, registers with an upper opening of the lower chamber. Upon clamping the housings together, the lower chamber is at least partially evacuated. The closure element is then moved to an open position and the welding unit is lowered into the evacuated lower chamber to weld a patch to the vessel wall to overlay the damaged area.

Abstract: An ultra high pressure abrasive waterjet cutting apparatus for cutting nuclear reactor structural components is described. The cutting apparatus includes an ultra high pressure abrasive waterjet (UHP) cutting nozzle, movably coupled to a single axis manipulator, and a collection hood. The manipulator and the collection hood are coupled to a support frame and are configured to be positioned inside adjacent openings of a nuclear reactor top guide or core plate so that the cutting nozzle is in alignment with the collection hood. The manipulator includes a linear frame, a nozzle support plate movably coupled to the linear frame, and a motor operatively coupled to the nozzle support plate. The collection hood includes an elongate collection chamber having an elongate opening located so that the opening is in alignment with the cutting nozzle.

Abstract: A core spray sparger for use in a nuclear reactor pressure vessel. The core spray sparger includes a plurality of core spray lines, a coupling apparatus, a bracket assembly, and an end clamp assembly. The core spray line includes a core spray line end cap.

Abstract: An ultra high pressure abrasive waterjet cutting apparatus for underwater cutting of structural components of a nuclear reactor is described. The cutting apparatus includes a multi-axis manipulator, an ultra high pressure abrasive waterjet (UHP) cutting nozzle coupled to the manipulator, a collection stand assembly, a collection hood movably coupled to the collection stand assembly, and a turntable having a non-movable center portion. The multi-axis manipulator is configured to mount on the non-movable center portion of the turntable or on the floor of the pool of water in which the structural component is positioned for cutting. The collection stand assembly is configured to mount on at least one of the floor and the wall of the pool of water. The cutting nozzle and collection hood are positioned on opposite sides of the structural component to be cut.

Abstract: The weld reinforcement includes a generally dogbone-shaped pocket having laterally enlarged end portions and a reduced intermediate portion spanning a weld seam. A complementary-shaped reinforcing element is received in the pocket. The pocket includes a projection which is received in an opening in the overlying reinforcing element. A wedge-type clamp retainer is received about the projection within the opening to secure the element within the pocket.

Abstract: A process and a system for detecting defective nuclear fuel assemblies in situ. The system includes two basic subsystems. The first subsystem is a sample collection system consisting of a hood placed over the fuel. A technique whereby a vacuum is drawn across a submerged nozzle of a degas tank is used to draw up the sample of fluid out of a fuel assembly. The second subsystem determines the amount of Kr-85 radioisotope contained in the fluid sample. This information is used to determine whether the fuel assembly contains a defective, i.e., leaking, fuel rod. The measurement values for Kr-85 in the fluid sample extracted from the fuel assembly are compared to the measurement values for Kr-85 in fluid samples taken from the reactor pool prior to fuel assembly testing and fluid samples taken from non-leaking control cells, the latter values representing the background to which the subject fuel assembly is compared.