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 decay station includes a housing comprising a radiation shielding. The housing delimits a decay conduit intended for containing the irradiation targets in the predetermined linear order. The decay conduit includes a decay conduit inlet, intended to be connected to the structure of the core of the nuclear reactor for receiving the irradiation targets therefrom; and a decay conduit outlet, intended to be connected to an irradiation target discharge system for discharging the irradiation targets from the decay station. The decay station further includes an inlet distributor, located at the decay conduit inlet, and configured for releasing only a predetermined amount of irradiation targets at a time from the decay station towards the structure of the core of the nuclear reactor. The inlet distributor is configured for releasing the irradiation targets closest to the decay conduit inlet, while retaining the remaining irradiation targets in the decay conduit. The decay station further includes an inlet counter configured for counting the number of irradiation targets entering or exiting the decay conduit through the decay conduit inlet. The inlet counter is located at the decay conduit inlet. The decay station further includes an outlet radiation detector configured for measuring the radiation emitted by an irradiation target located at the decay conduit outlet.

A decay station includes a housing comprising a radiation shielding. The housing delimits a decay conduit intended for containing the irradiation targets in the predetermined linear order. The decay conduit includes a decay conduit inlet, intended to be connected to the structure of the core of the nuclear reactor for receiving the irradiation targets therefrom; and a decay conduit outlet, intended to be connected to an irradiation target discharge system for discharging the irradiation targets from the decay station. The decay station further includes an inlet distributor, located at the decay conduit inlet, and configured for releasing only a predetermined amount of irradiation targets at a time from the decay station towards the structure of the core of the nuclear reactor. The inlet distributor is configured for releasing the irradiation targets closest to the decay conduit inlet, while retaining the remaining irradiation targets in the decay conduit. The decay station further includes an inlet counter configured for counting the number of irradiation targets entering or exiting the decay conduit through the decay conduit inlet. The inlet counter is located at the decay conduit inlet. The decay station further includes an outlet radiation detector configured for measuring the radiation emitted by an irradiation target located at the decay conduit outlet.

An irradiation facility for a nuclear reactor, a method of removing thermal heat from an irradiated object and adjusting an energy distribution/neutron/gamma-ray flux ratio of irradiation, and a product obtainable by the method.

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.

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.

Disclosed are a radioisotope activity surveillance system and methods. The system includes a fuel rod assembly having a plurality of nuclear fuel rods and a target assembly having a top nozzle including an orifice plate and at least one target material rod fixedly coupled to the orifice plate. The least one target material rod is slidably disposed within the fuel rod assembly. A sensing assembly defines an opening sized and configured to receive the target assembly therethrough. The sensing assembly includes a self-powered detector assembly to detect radioisotope activity of the target rod material. Also disclosed is a method for measuring a self-powered detector signal to calculate radioisotope activity of a target assembly and a method for analyzing total activity of a desired radioisotope.

A fuel bundle surrogate for the irradiation of a target material, having a plurality of tube sheaths, each tube sheath being parallel to a longitudinal center axis of the fuel bundle surrogate, a plurality of end caps, a pair of end plates, wherein the end plates are disposed at opposing ends of the plurality of tube sheaths, and a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, wherein the first target is disposed in a first tube sheath, and wherein the first tube sheath of the plurality of tube sheaths comprises an elongated thickened wall portion and a pair of annular end portions, each annular end portion being disposed on a corresponding end of the thickened wall portion and having a wall thickness that is less than a wall thickness of the thickened wall portion.

A fuel bundle surrogate for the irradiation of a target material, having a plurality of tube sheaths, each tube sheath being parallel to a longitudinal center axis of the fuel bundle surrogate, a plurality of end caps, a pair of end plates, wherein the end plates are disposed at opposing ends of the plurality of tube sheaths, and a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, wherein the first target is disposed in a first tube sheath, and wherein the first tube sheath of the plurality of tube sheaths comprises an elongated thickened wall portion and a pair of annular end portions, each annular end portion being disposed on a corresponding end of the thickened wall portion and having a wall thickness that is less than a wall thickness of the thickened wall portion.

A device that will enable material to be irradiated as needed to produce a desired transmutation product inside the core of a nuclear reactor. The device provides a means for monitoring neutron flux in the vicinity of the material being irradiated to allow determination of the amount of transmutation product being produced. The device enables the irradiated material to be inserted into the reactor and held in place at desired axial positions and to be withdrawn from the reactor when desired without shutting down the reactor. The majority of the device may be re-used for subsequent irradiations. The device also enables the simple and rapid attachment of unirradiated target material to the portion of the device that transmits the motive force to insert and withdraw the target material into and out of the reactor and the rapid detachment of the irradiated material from the device for processing.