A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

A method of replacing a damaged thermal sleeve in a reactor vessel head adapter that connects a control rod drive mechanism to a reactor vessel head includes the steps of accessing the damaged thermal sleeve, removing the damaged thermal sleeve, and obtaining a replacement thermal sleeve having an elongated tubular body, a flanged region, and a plurality of slots defined in the elongated tubular body, each slot having a width which is sufficient to narrow a maximum outside diameter of the flanged region from a first diameter to a second diameter. The method further includes altering the maximum outside diameter of the flanged region on the replacement thermal sleeve, inserting the replacement thermal sleeve into an opening of a tubular member from an underside of the reactor vessel head, and expanding the maximum outside diameter of the flanged region into a recess of the reactor vessel head adapter.

A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod.

An apparatus for removing foreign substances around a heating tube of a steam generator is proposed. The apparatus includes a universal machine unit configured to hold the foreign substances, a connecting rod unit including a distal end connecting rod and a connecting rod part, a connecting rod moving unit configured to supply the connecting rod unit into the heating tube to move the connecting rod unit, a connecting rod supply unit provided to sequentially supply the plurality of connecting rods to the connecting rod moving unit, an image-capturing unit configured to be moved to a point where the foreign to substances are located to capture an image of the foreign substances, and a controller connected to the universal machine unit, the connecting rod moving unit, and the connecting rod supply unit to control operations thereof.

A method of removing floating foreign substances that may interfere with a normal operation of an electromechanical mechanism of a control rod drive mechanism and a device for executing the same are provided. The method of removing the foreign substances from the control rod drive mechanism comprising a driving shaft including a plurality of teeth and disposed in a vertical direction in the control rod drive mechanism, a first part configured to hold or release a lower end portion of the driving shaft depending on whether a stationary gripper coil is activated, a second part configured to hold or release an intermediate portion of the driving shaft depending on whether a movable gripper coil is activated, and a third part configured to move the second part in the vertical direction depending on whether a lift coil is activated may include: activating at least one of the stationary gripper coil, the movable gripper coil, and the lift coil to drive the first part, the second part, or the third part in a state in which the driving shaft is not able to move; and removing the foreign substances from the first part, the second part, or the third part.

A mobile robotic assembly for guiding an end effector in inspecting reactor vessel heads is disclosed. The mobile robotic assembly includes a mobile platform; a support assembly extending vertically from the mobile platform, wherein the support assembly comprises an adjustable height; and a robotic arm attached to and extending laterally from the support assembly.

A method of cleaning a jet pump assembly of a nuclear reactor may comprise inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly. The method may additionally comprise directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid strikes the inner surface of the jet pump assembly. The method may further comprise maintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly.

The invention refers to the area of nuclear power engineering, particularly to auxiliary devices for nuclear power plants, namely to the devices for installation of the outer heat insulation of a nuclear reactor vessel, and can be used at nuclear plants for recovery annealing of the VVER reactor vessel welds.

The objective to be achieved with the use of the claimed invention is to provide the possibility for installation and dismantling of heat insulation on the outer surface of the VVER reactor vessel in the confined space of the subpile room and at the increased level of ionizing radiation.

Reduction of the temperature gradient through the thickness of the nuclear reactor vessel by heat insulation of the external reactor vessel surface, assurance of uniform physical properties for the reactor vessel metal and welds and reduction of thermal impacts on the surrounding structures during recovery annealing of the welds and/or base metal of the VVER reactor vessel shall be the technical result of this invention.

The technical result of the invention is ensured by the fact that the device for installation of the outer heat insulation of a nuclear reactor vessel includes a mobile transfer trolley equipped with the mechanism for its movement, a removable bearing rim located on the mobile transfer trolley with the reactor vessel heat insulation attached to it, at least two lifting devices located on the opposite sides of the reactor vessel at the level of its upper section, in this case the removable bearing rim is connected to the lifting devices with the possibility to lift and lower it.

Application of the claimed invention will provide the possibility for installation and dismantling of heat insulation on the outer surface of the VVER reactor vessel in the confined space of the subpile room and at the increased level of ionizing radiation. Heat insulation of the external reactor vessel surface will ensure reduction of the temperature gradient through the thickness of the nuclear reactor vessel, uniformity of the physical properties for its metal and welds as well as reduction of thermal impacts on the surrounding structures during recovery annealing of the welds and/or base metal of the VVER reactor vessel.