An irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core comprises, a target retrieving system, target insertion system and transport gas supply system, mounted on a movable support, wherein: the target retrieving system comprises a target exit port coupled to a target storage container and exhaust system; the target insertion system comprises a target filling device, target retention tubing with target supply junction connectable to the instrumentation tube, and a target diverter coupled to the target filling device, target retention tubing and target retrieving system; and the transport gas supply system comprises a first gas supply tubing coupled to the exit port of the target retrieving system, a second gas supply tubing coupled to a junction for supplying gas to the instrumentation tube, and a transport gas supply junction coupled to the first and second gas supply tubing.

An irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core comprises, a target retrieving system, target insertion system and transport gas supply system, mounted on a movable support, wherein: the target retrieving system comprises a target exit port coupled to a target storage container and exhaust system; the target insertion system comprises a target filling device, target retention tubing with target supply junction connectable to the instrumentation tube, and a target diverter coupled to the target filling device, target retention tubing and target retrieving system; and the transport gas supply system comprises a first gas supply tubing coupled to the exit port of the target retrieving system, a second gas supply tubing coupled to a junction for supplying gas to the instrumentation tube, and a transport gas supply junction coupled to the first and second gas supply tubing.

A target irradiation system including an irradiated target removal system having a body defining a central bore, an elevator received within the central bore, and a docking surface for placing the irradiated target removal system in fluid communication with a vessel penetration of a reactor. A target canister slidably receives the radioisotope target therein, and the elevator is configured to receive the target canister. The elevator is lowered into the reactor when irradiating the radioisotope target, and the irradiated target removal system forms a portion of a pressure boundary of the reactor during target irradiation.

A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.

A mounting assembly that has no threaded connections. A rod with pins or machined features radially extending from a distal end is configured to rotate until the pins align with grooves in a hole through a base plate. The rod is inserted through the hole until the pins are through an opposite surface of the base plate, compressing spring components on the rod. Then the rod is rotated until the pins are aligned with slots that partially extend through the second side of the base plate and the pins become seated in the slots. To remove the rod a tool that engages an articulated feature on the distal end of the rod is installed. The tool rotates the rod until the pins are disengaged from the slots, aligned with the through grooves and passed through the base plate.

A mounting assembly that has no threaded connections. A rod with pins or machined features radially extending from a distal end is configured to rotate until the pins align with grooves in a hole through a base plate. The rod is inserted through the hole until the pins are through an opposite surface of the base plate, compressing spring components on the rod. Then the rod is rotated until the pins are aligned with slots that partially extend through the second side of the base plate and the pins become seated in the slots. To remove the rod a tool that engages an articulated feature on the distal end of the rod is installed. The tool rotates the rod until the pins are disengaged from the slots, aligned with the through grooves and passed through the base plate.

Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons ?0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.

Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons ?0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.

An apparatus for removing irradiated Co-60 capsules from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome a plurality of forces exerted on it.

A means for installing material, through a fuel assembly instrument thimble insert, into the existing instrument thimbles in nuclear fuel assemblies for the purpose of allowing the material to be converted to commercially valuable quantities of desired radioisotopes during reactor power operations during a remainder of a fuel cycle and removing the radioisotopes from the core through the reactor flange opening once the fuel assemblies have been removed for refueling. The invention also describes methods that can be used to harvest the irradiated material so it can be packaged for transportation from the reactor to a location where the desired radioisotope(s) can be extracted from the fuel assembly instrument thimble insert.