G21C19/105

IN-VESSEL CORE COMPONENT HANDLING SYSTEMS AND METHODS

An in-vessel fuel transfer machine may be permanently affixed to a nuclear reactor and remain in place during power operations. The in-vessel fuel transfer machine may include a pantograph machine that positions a grapple in order to access any fuel socket location within the core and move any of the core assemblies between the core, an in-vessel fuel storage area, and a fuel elevator. The grapple may be positioned through a combination of movements, such as, rotating a rotating plug assembly, rotating the in-vessel fuel transfer machine, extending the pantograph arms, and shuttling the grapple along a leg. The grapple may be compliant to accommodate deformed core assemblies and may be configured to pivot to more closely align to an eccentric core assembly handling socket or be moveable in a horizontal plane to accommodate a deformed core assembly during insertion or withdrawal.

Mechanical grasping end effector with linear engagement and disengagement movement
12125600 · 2024-10-22 · ·

A mechanical device for grasping an object includes a receiver having a distal end shaft with an internal bore, the internal bore defining a recessed track. The recessed track defines a curvilinear path having two sets of resting peaks, each set of resting peaks being at a different height relative to a centerline of the curvilinear path. An actuator is slidably engaged with the receiver and includes a central shaft and an activator disposed at a distal end portion of the central shaft. A rotatable sleeve is disposed within the internal bore of the receiver and is coupled to the actuator. The rotatable sleeve has opposed protrusions, the opposed protrusions being disposed within the recessed track of the receiver. A pilot is secured to a distal end portion of the receiver and a grasping device is mounted to the pilot and coupled to the activator.

Mechanical grasping end effector with linear engagement and disengagement movement
12125600 · 2024-10-22 · ·

A mechanical device for grasping an object includes a receiver having a distal end shaft with an internal bore, the internal bore defining a recessed track. The recessed track defines a curvilinear path having two sets of resting peaks, each set of resting peaks being at a different height relative to a centerline of the curvilinear path. An actuator is slidably engaged with the receiver and includes a central shaft and an activator disposed at a distal end portion of the central shaft. A rotatable sleeve is disposed within the internal bore of the receiver and is coupled to the actuator. The rotatable sleeve has opposed protrusions, the opposed protrusions being disposed within the recessed track of the receiver. A pilot is secured to a distal end portion of the receiver and a grasping device is mounted to the pilot and coupled to the activator.

Method for shielded relocation of a nuclear component

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.

Method for shielded relocation of a nuclear component

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.

METHOD OF EXTRACTING PLUG AND REMOVABLE UNIT WHEN REFUELING NUCLEAR REACTOR

A method of the plug and removable block extraction when reloading the nuclear reactor. The invention relates to nuclear engineering, in particular to a process of the plug and the removable block extraction from a fast reactor with a heavy liquid metal coolant. The technical result consists in extracting the plug and the removable block without fuel assemblies from the nuclear reactor using a complex of handling equipment under radiation safety conditions. The method of the plug removable block extraction involves preliminary installation of handling equipment, removing the plug from the reactor monoblock, as well as transportation and positioning of the plug in the plug shaft, unloading the removable block, its transportation and placing the removable block in the shaft for the removable block disassembly.

METHOD OF EXTRACTING PLUG AND REMOVABLE UNIT WHEN REFUELING NUCLEAR REACTOR

A method of the plug and removable block extraction when reloading the nuclear reactor. The invention relates to nuclear engineering, in particular to a process of the plug and the removable block extraction from a fast reactor with a heavy liquid metal coolant. The technical result consists in extracting the plug and the removable block without fuel assemblies from the nuclear reactor using a complex of handling equipment under radiation safety conditions. The method of the plug removable block extraction involves preliminary installation of handling equipment, removing the plug from the reactor monoblock, as well as transportation and positioning of the plug in the plug shaft, unloading the removable block, its transportation and placing the removable block in the shaft for the removable block disassembly.

MECHANICAL GRASPING END EFFECTOR WITH LINEAR ENGAGEMENT AND DISENGAGEMENT MOVEMENT
20250046482 · 2025-02-06 · ·

A mechanical device for grasping an object that includes a receiver, an actuator, a rotatable sleeve, a pilot, and a grasping device. The receiver includes a distal end shaft having an internal bore. The internal bore defines a recessed track. The actuator is slidably engaged with the receiver. The rotatable sleeve is disposed within the internal bore of the receiver and is coupled to the actuator. The rotatable sleeve includes at least one protrusion. The protrusion is disposed within the recessed track of the receiver. The pilot is secured to a distal end portion of the receiver. The grasping device is mounted to the pilot.

MECHANICAL GRASPING END EFFECTOR WITH LINEAR ENGAGEMENT AND DISENGAGEMENT MOVEMENT
20250046482 · 2025-02-06 · ·

A mechanical device for grasping an object that includes a receiver, an actuator, a rotatable sleeve, a pilot, and a grasping device. The receiver includes a distal end shaft having an internal bore. The internal bore defines a recessed track. The actuator is slidably engaged with the receiver. The rotatable sleeve is disposed within the internal bore of the receiver and is coupled to the actuator. The rotatable sleeve includes at least one protrusion. The protrusion is disposed within the recessed track of the receiver. The pilot is secured to a distal end portion of the receiver. The grasping device is mounted to the pilot.

FUEL ASSEMBLY FOR A NUCLEAR POWER PLANT, METHOD FOR ACTIVATING A MATERIAL TO BE ACTIVATED AND GRIPPER
20250069763 · 2025-02-27 ·

A fuel assembly (1) for a nuclear power plant includes at least one hollow rod (9, 9a,9b, 9c). The hollow rod is a control rod guide tube (9) of the fuel assembly (1) for the control rod assembly or an instrumentation tube. Each rod (9) is adapted to be filled with one or more containers (38) filled with material to be activated. The fuel assembly further comprises a damping element (36, 36a, 36b, 36c) at the lower end (32) of the hollow rod (9, 9a,9b, 9c).