The method includes installing a system for inspecting the core shroud on the core shroud, driving the system horizontally around the core shroud, and using a sensor of the system to inspect the core shroud, where the system includes a trolley, an arm, a tether, and a remotely operated vehicle (ROV) for inspecting the core shroud. The ROV includes a body configured to be operatively connected to the tether, and the sensor is configured to be operatively connected to the body, and configured to provide inspection information of the core shroud. The arm is configured to be operatively connected to the trolley. The ROV is configured to be operatively connected to the arm via the tether, and the tether is configured to provide vertical position information for the ROV relative to the outer surface of the core shroud.

In a WJP execution method for a reactor vessel lid, WJP is executed on the inner surface of the reactor vessel lid in a state in which an underwater environment is formed on the inner surface of the reactor vessel lid and an aerial environment is formed on the outer surface thereof. In addition, the reactor vessel lid with a waterproof jig attached thereto is arranged in water, the waterproof jig having a cylindrical shape extending to the side of the outer surface of the reactor vessel lid and constituting a vessel with the reactor vessel lid as the bottom portion thereof. Moreover, the reactor vessel lid is arranged on a base installed in the water.

In a WJP execution method for a reactor vessel lid, WJP is executed on the inner surface of the reactor vessel lid in a state in which an underwater environment is formed on the inner surface of the reactor vessel lid and an aerial environment is formed on the outer surface thereof. In addition, the reactor vessel lid with a waterproof jig attached thereto is arranged in water, the waterproof jig having a cylindrical shape extending to the side of the outer surface of the reactor vessel lid and constituting a vessel with the reactor vessel lid as the bottom portion thereof. Moreover, the reactor vessel lid is arranged on a base installed in the water.

A nuclear plant manipulator system, including a manipulator with an image acquisition device and a remotely-controlled drive, wherein the image acquisition device is configured to capture image data, a remote-operating device is configured to remotely control the manipulator, an object counter is configured to be incremented or decremented, and an analysis device is configured to receive the image data captured by the image acquisition device and evaluate the received image data. The analysis device is configured to automatically identify respective known objects that are found along a path while the manipulator moves along the path. When a respective known object along the path is passed by the manipulator, the object counter is incremented or decremented depending on the direction of the manipulator along the path. A current value of the object counter is provided to the remote-operating device.

A nuclear plant manipulator system, including a manipulator with an image acquisition device and a remotely-controlled drive, wherein the image acquisition device is configured to capture image data, a remote-operating device is configured to remotely control the manipulator, an object counter is configured to be incremented or decremented, and an analysis device is configured to receive the image data captured by the image acquisition device and evaluate the received image data. The analysis device is configured to automatically identify respective known objects that are found along a path while the manipulator moves along the path. When a respective known object along the path is passed by the manipulator, the object counter is incremented or decremented depending on the direction of the manipulator along the path. A current value of the object counter is provided to the remote-operating device.

Systems are provided for inspection and tooling submerged in nuclear reactors. Systems mount at the reactor edge, such as on a steam dam, to be independently operable from a refueling bridge or refueling operations. A moveable steam dam clamp may hold a position apparatus at the edge. The positioning apparatus includes a rotatable shoulder and arms move a tool, reactor component, and/or inspection device like a camera or VARD to desired and highly-determinable reactor positions. A float may counter shear and rotation on the shoulder from the arms. Motors at the shoulder with internal transmissions may rotate the shoulder and arms, or manual rotation may be used. The arms may also overlap vertically for installation and removal. Power, controls, and/or data may be provided underwater through an umbilical connection to operators.

A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor, an inert gas is applied to the fuel assembly, moisture content in the inert gas is gradually increased as it is applied to the fuel assembly, and the fuel assembly is immersed in water. The fuel assembly is immersed relatively quickly, within about 2 hours or less, which improves safety and allows normal processing and handling equipment to care for the fuel assembly. The fuel assembly may then be loaded into a cask for long-term storage and/or disposal.

An assembly for acting on the outer surface of a tube, and corresponding method are provided. The assembly includes a carrier; at least one inspection or maintenance tool; the carrier includes at least one rolling body; an actuator. The carrier further includes a device for connecting the carrier to the tube, arranged so that the tube absorbs at least 50% of the weight of the carrier and the tool.

A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums.

Provided is a water jet peening apparatus and a water jet peening method including: a clamping cylinder (201) which is able to be disposed at the outer peripheral side of an instrumentation nozzle (83) with a predetermined gap therebetween; a clamping piece (210) which is able to fix the clamping cylinder (201) to the instrumentation nozzle (83); a nozzle guide (221) which has a cylindrical shape, is provided inside the clamping cylinder (201), and is positioned to a position adjacent to the upper end of the instrumentation nozzle (83); an inner surface WJP nozzle (105) which is movable upward and downward inside the nozzle guide (221); and a drainage hole (224) which radially penetrates the nozzle guide (221). Accordingly, it is possible to improve the safety of the operation by preventing a thimble tube from being popped out due to a water jet peening operation.