Patent classifications
G21C23/00
Irradiating target material located in a surrogate fuel bundle in a CANDU reactor for isotope production
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.
Irradiating target material located in a surrogate fuel bundle in a CANDU reactor for isotope production
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.
Radioisotope production target insert design and target harvesting methodology for long term irradiation in commercial nuclear reactors
A device and method that enables a specimen that is to be converted into a radioisotope to be inserted into an extended, retractable thimble of a nuclear reactor moveable in-core detector system and be harvested after irradiation either during reactor operation or a refueling outage without damaging the retractable thimble. The specimen is enclosed within the interior of a forward portion of a tubular member having a closed lead end and structured to travel within the retractable thimble. The tubular member is sized to extend from a position above and proximate the desired core elevation the specimen is to be irradiated at to a location above a seal table that the retractable thimble extends through. The specimen is inserted and withdrawn from the core by inserting or withdrawing the tubular member from above the seal table. Desirably, the forward end of the tubular member is divided into several specimen compartments.
Radioisotope production target insert design and target harvesting methodology for long term irradiation in commercial nuclear reactors
A device and method that enables a specimen that is to be converted into a radioisotope to be inserted into an extended, retractable thimble of a nuclear reactor moveable in-core detector system and be harvested after irradiation either during reactor operation or a refueling outage without damaging the retractable thimble. The specimen is enclosed within the interior of a forward portion of a tubular member having a closed lead end and structured to travel within the retractable thimble. The tubular member is sized to extend from a position above and proximate the desired core elevation the specimen is to be irradiated at to a location above a seal table that the retractable thimble extends through. The specimen is inserted and withdrawn from the core by inserting or withdrawing the tubular member from above the seal table. Desirably, the forward end of the tubular member is divided into several specimen compartments.
FISSILE TARGET MATERIALS AND METHODS FOR PROCESSING FISSILE TARGET MATERIALS
Methods for preparing fissile target materials are provided. The methods can include preparing a target substrate that includes a fissile atom, and layering at least one surface of the substrate with a capturing layer. Fissile target materials are provided. The fissile target materials can include a target substrate and a capturing layer operably interfacing with at least one surface of the target substrate. Methods for fissioning fissile target materials are also provided. The methods can include irradiating fissile target material to capture fission products of the irradiated fissile target material in a capturing layer of the target material. Fission fissile target materials are also provided that can include a target substrate comprising at least one fissile atom and a capturing layer operably interfacing with at least one surface of the target substrate. The capturing layer can include at least one fission product. Methods for separating fissioned product from fission fissile target materials are also provided. The methods can include separating at least a portion of the captured layer of the fissioned fissile target material from the fissile target material.
FISSILE TARGET MATERIALS AND METHODS FOR PROCESSING FISSILE TARGET MATERIALS
Methods for preparing fissile target materials are provided. The methods can include preparing a target substrate that includes a fissile atom, and layering at least one surface of the substrate with a capturing layer. Fissile target materials are provided. The fissile target materials can include a target substrate and a capturing layer operably interfacing with at least one surface of the target substrate. Methods for fissioning fissile target materials are also provided. The methods can include irradiating fissile target material to capture fission products of the irradiated fissile target material in a capturing layer of the target material. Fission fissile target materials are also provided that can include a target substrate comprising at least one fissile atom and a capturing layer operably interfacing with at least one surface of the target substrate. The capturing layer can include at least one fission product. Methods for separating fissioned product from fission fissile target materials are also provided. The methods can include separating at least a portion of the captured layer of the fissioned fissile target material from the fissile target material.
System and method for harvesting of activated irradiation targets from a nuclear reactor and radionuclide generation system
A method for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor comprises: Coupling the instrumentation tube system to a discharge tube having an apex, exit port and lock element between the apex and exit port; Passing the activated irradiation targets from the instrumentation tube system into the discharge tube and blocking movement of said targets out of the discharge tube using the lock element; Separating a predefined quantity of the targets from another quantity of targets in the discharge tube by passing the predefined quantity of targets over the apex, retaining the remainder in the discharge tube by means of the apex; Coupling the exit port to a storage container and releasing the lock element to pass via gravity the predefined quantity of targets into the storage container. Systems for generating radionuclides and harvesting activated irradiation targets adapted to the above method are also provided.
System and method for harvesting of activated irradiation targets from a nuclear reactor and radionuclide generation system
A method for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor comprises: Coupling the instrumentation tube system to a discharge tube having an apex, exit port and lock element between the apex and exit port; Passing the activated irradiation targets from the instrumentation tube system into the discharge tube and blocking movement of said targets out of the discharge tube using the lock element; Separating a predefined quantity of the targets from another quantity of targets in the discharge tube by passing the predefined quantity of targets over the apex, retaining the remainder in the discharge tube by means of the apex; Coupling the exit port to a storage container and releasing the lock element to pass via gravity the predefined quantity of targets into the storage container. Systems for generating radionuclides and harvesting activated irradiation targets adapted to the above method are also provided.
Irradiation target handling device for moving a target into a nuclear reactor
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.
Nuclear powered vacuum microelectronic device
A vacuum micro-electronics device that utilizes fissile material capable of using the existing neutron leakage from the fuel assemblies of a nuclear reactor to produce thermal energy to power the heater/cathode element of the vacuum micro-electronics device and a self-powered detector emitter to produce the voltage/current necessary to power the anode/plate terminal of the vacuum micro-electronics device.