Abstract: Provided herein are high energy ion beam generator systems and methods that provide low cost, high performance, robust, consistent, uniform, low gas consumption and high current/high-moderate voltage generation of neutrons and protons. Such systems and methods find use for the commercial-scale generation of neutrons and protons for a wide variety of research, medical, security, and industrial processes.

Abstract: A target well of a target delivery assembly for use in an irradiation system operative to allow irradiation of a radioisotope target via a vessel penetration of a fission reactor. The target well includes an outer tube and an inner tube disposed therein so that an annulus is formed therebetween. The target is positioned in the inner tube during irradiation. At least one flow channel extends between a bottom end of the outer tube and a bottom end of the inner tube. An elevation piston is slidably disposed within the inner tube to elevate the target, the elevation piston including a one-way check valve allowing flow in a downward direction and preventing flow in an upward direction.

Abstract: An annular radioisotope target and method therefor that includes an inner cladding tube and a helical coil-shaped foil ribbon disposed over the inner cladding tube. The helical coil-shaped foil ribbon has a first end, a second end, a first edge and a second edge. An outer cladding tube is disposed over the helical coil-shaped foil ribbon and inner cladding tube, and end caps are attached to the outer cladding tube and the inner cladding tube.

Abstract: Provided is a method capable of separating and purifying astatine-211 in a high yield and dissolving same in a solution. A method for producing astatine-211, including a step of irradiating ? ray to bismuth to produce astatine-211 in the bismuth, and a step of distilling the bismuth that received ? ray irradiation with a carrier gas containing an inert gas, O2 and H2O to separate and purify astatine-211, and dissolving the astatine-211 in a solution.

Abstract: 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.

Abstract: Provided herein are systems, devices, articles of manufacture, and methods for generating neutrons employing a high energy ion beam target (HEIB target) and a target backing configured to be in contact with the bottom surface of the HEIB target (e.g., to generate an ion beam target assembly). In certain embodiments, the HEIB target has a thickness that is less than the penetration depth of protons or deuterons in the high energy ion beam that strikes the target. In certain embodiments, the target backing comprises a high hydrogen diffusion metal (e.g., palladium), has open spaces dispersed throughout for reduced proton diffusion distances, and has a shape and thickness such that all, or virtually all, of the protons or deuterons that pass through the HEIB target are stopped. Also provided herein are systems, devices, and methods for changing targets in an ion beam accelerator system.

Abstract: Provided herein are systems and methods for generating a plurality of different monoenergetic neutron energies using a plurality of interchangeable ion beam targets. In certain embodiments, each of the plurality of ion beam targets is configured to generate a monoenergetic energy value that is at least 100 kiloelectron volts (keV) different from the other ion beam targets. In some embodiments, the ion beam targets are composed of LiF, TiD1.5-1.8, TiT1-2, ErD1.5, ErT, or Li.

Abstract: 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.

Abstract: The present disclosure provides a method and an apparatus for producing astatine-211 from alpha-particle bombardment of bismuth-209. The disclosure also relates to a method and apparatus of producing other radionuclides from target nuclides. The apparatus includes a plate having a recessed portion. The recessed portion has a generally inert surface of ceramic or metal, preferably aluminium oxide that does not react with molten bismuth. A bismuth target is placed in the recessed portion and held therein by a foil cover. The foil has a melting temperature greater than target nuclide (i.e., for bismuth, >271° C.). The foil and target nuclide are held in the recessed portion by a cover that is fastened over the foil. The cover has an aperture to allow a beam of radiation, such as alpha particles, from a cyclotron or other accelerator to pass through the cover to the foil and target nuclide.

Abstract: 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.

Abstract: 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.

Abstract: A canister to store spent nuclear fuel in an underground repository includes a first end portion; a second end portion; and a middle portion attachable to the first and second end portions to define an interior volume of the housing that is sized to enclose at least one spent nuclear fuel assembly. The first and second end portions comprise shielding.

Abstract: 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.

Abstract: A nuclear reactor is operated with irradiation target holders fit in open locations inside of an operating commercial nuclear core and placed with ends at vertical bottom and top of the core or any position therebetween to directly expose holders to nuclear fuel reactions. Holders have ends and overall shape that are joined with existing reactor structures, while fitting closely with fuel and moderator and being easily removable from the same. Holders are fabricated of any reactor-compatible material that will retain irradiation targets and daughter products. Holders securely retain irradiation targets and daughter products of any shape or phase throughout reactor operation. Holders can be installed during reactor outages and irradiated during operation without risk of movement or interference with operation. After a desired period of operation and irradiation, holders can be harvested from the core independent of other core structures and fuel.

Abstract: The invention relates to an implantable stomach prosthesis for surgically replacing or augmenting all or part of the antrum and/or pylorus of a stomach. The prosthesis controls the passage of food from the stomach to the small intestine. The prosthesis may be configured to churn ingested material and release it from the stomach through a prosthetic pyloric valve. At least one expandable member is arranged to be expanded to control the passage of food and/or to mimic the churning action of a patient's stomach. The prosthesis includes an outer support structure, a flexible inner member forming a conduit for the movement of material, and at least one expandable member located between the outer support structure and inner member. An implantable pump system is provided for inflating and deflating the expandable member(s).

Abstract: Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include irradiation targets for producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more irradiation targets useable with example delivery systems that permit delivery into instrumentation tubes. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while producing desired isotopes.

Abstract: The invention relates to an implantable stomach prosthesis for surgically replacing or augmenting all or part of the antrum and/or pylorus of a stomach. The prosthesis controls the passage of food from the stomach to the small intestine. The prosthesis may be configured to churn ingested material and release it from the stomach through a prosthetic pyloric valve. At least one expandable member is arranged to be expanded to control the passage of food and/or to mimic the churning action of a patient's stomach. The prosthesis includes an outer support structure, a flexible inner member forming a conduit for the movement of material, and at least one expandable member located between the outer support structure and inner member. An implantable pump system is provided for inflating and deflating the expandable member(s).

Abstract: Example embodiments are directed to materials useable as burnable poisons in nuclear reactors, components using the same, and methods of using the same. Example embodiment burnable poison materials produce desired daughter products as they burn out, thereby permitting placement and use for neutronic characteristic improvement and/or neutron flux shielding in locations conventionally barred as uneconomical. Example embodiment burnable poison materials may include natural iridium and enriched iridium-193. Example embodiment components may be fabricated, shaped, and placed to provide desired burnable poison effects in the reactor core in conventional locations and locations not conventionally used due to economic infeasibility.

Abstract: In a method of producing isotopes in a light water power reactor, one or more targets within the reactor may be irradiated under a neutron flux to produce one or more isotopes. The targets may be assembled into one or more fuel bundles that are to be loaded in a core of the reactor at a given outage. Power operations in the reactor irradiate the fuel bundles so as to generate desired isotopes, such as one or more radioisotopes at a desired specific activity or stable isotopes at a desired concentration.

Abstract: An apparatus for producing 99Mo from a plurality of 100Mo targets through a photo nuclear reaction on the 100Mo targets. The apparatus comprises: (i) an electron linear accelerator component; (ii) an energy converter component capable of receiving the electron beam and producing therefrom a shower of bremsstrahlung photons; (iii) a target irradiation component for receiving the shower of bremsstrahlung photons for irradiation of a target holder mounted and positioned therein, The target holder houses a plurality of 100Mo target discs. The apparatus additionally comprises (iv) a target holder transfer and recovery component for receiving, manipulating and conveying the target holder by remote control; (v) a first cooling system sealingly engaged with the energy converter component for circulation of a coolant fluid therethrough; and (vi) a second cooling system sealingly engaged with the target irradiation component for circulation of a coolant fluid therethrough.

Abstract: A rod assembly for a fuel bundle of a nuclear reactor may include an upper end piece, lower end piece and a plurality of rod segments attached between the upper and lower end pieces and to each other so as to form an axial length of the rod assembly. The rod assembly may include an adaptor subassembly provided at given connection points for connecting adjacent rod segments or a given rod segment with one of the upper and lower end pieces. The connection points along the axial length of the rod assembly may be located where the rod assembly contacts a spacer in the fuel bundle. One (or more) of the rod segments may include an irradiation target therein for producing a desired isotope when a fuel bundle containing one (or more) rod assemblies is irradiated in a core of the reactor.

Abstract: There is provided a quench tank which is disposed in a circulation path of a liquid metal loop and separates and cools liquid metal steam or a mixed gas in liquid metal introduced into a tank body. The tank body includes a separating area which forms a substantially horizontal flow of the liquid metal, and a separating plate is disposed inside the tank body so as to be inclined with respect to the vertical direction.

Abstract: A capsule for holding, irradiating, and eluting a material is provided. Methods of fabricating and using the capsule are also provided. The capsule may include a multidiameter tube with a first end region, a second end region, and a middle region. Washers and filters are provided in the end regions and the end regions may be sealed using various methods and materials with the end caps press fit into the end regions. The middle region is designed to store a material to be irradiated by a neutron flux source. The capsule components may be made from materials having a low nuclear cross section so that the capsule may be handled safely after an irradiation step is performed. The capsule is also designed to have a symmetric configuration as an elution and irradiation column so that the same capsule may be used to elute the material within the middle region of the capsule after an irradiation step is performed.

Abstract: A capsule for holding, irradiating, and eluting a material is provided. Methods of fabricating and using the capsule are also provided. The capsule may include a multidiameter tube with a first end region, a second end region, and a middle region. Washers and filters are provided in the end regions and the end regions may be sealed using various methods and materials with the end caps press fit into the end regions. The middle region is designed to store a material to be irradiated by a neutron flux source. The capsule components may be made from materials having a low nuclear cross section so that the capsule may be handled safely after an irradiation step is performed. The capsule is also designed to have a symmetric configuration as an elution and irradiation column so that the same capsule may be used to elute the material within the middle region of the capsule after an irradiation step is performed.

Abstract: A particle beam target for producing radionuclides includes a target body, a target cavity, parallel grooves, peripheral bores, and radial outflow bores. The parallel grooves are formed in a back side of the target body and include respective first and second groove ends. The peripheral bores extend through the target body from the plurality of grooves generally toward the front side that receives a particle beam. Each groove communicates with a peripheral bore at the first groove end and another peripheral bore at the second groove end. The radial outflow bores extend radially from the plurality of peripheral bores. The target body defines a plurality of liquid coolant flow paths. Each liquid coolant flow path runs from a respective groove to at least one of the first groove end and the second groove end of the respective groove, through at least one peripheral bore, and through at least one radial outflow bore.

Abstract: Apparatus for generating thermal neutrons includes an electron accelerator for generating an electron beam and a converter for converting the electron beam into photons. A receiving device is provided for receiving the photons and includes a material which provides a photoneutron target for the photons, for producing high energy neutrons in a photonuclear reaction between the photons and the photoneutron target, and for moderating the high energy neutrons to generate the thermal neutrons. The electron beam has an energy level high enough to produce photons of sufficient energy to exceed the photodissociation threshold of the selected target material, but that is sufficiently low as to enable the material to moderate the high energy neutrons resulting from the photonuclear reaction.

Abstract: A target assembly for irradiating Zn68 with high energy gamma rays to form Cu67 is described. The assembly comprises a Zn68 target mass, optionally housed within in a water-tight chamber, the assembly including a plurality of parallel external cooling fins in contact with the Zn68 target mass or the chamber, the Zn68 target mass being removable from the assembly, or separable from the plurality of cooling fins when no chamber is present, so that Cu67 can be isolated from the Zn68 after irradiation.

Abstract: Apparatuses and methods produce radioisotopes in multiple instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from multiple instrumentation tubes during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation tubes during operation of the nuclear plant. Example systems can simultaneously maintain irradiation targets in multiple instrumentation tubes for desired irradiation followed by harvesting.

Abstract: Example embodiments are directed to tie plate attachments having irradiation targets and/or fuel assemblies having example embodiment tie plate attachments with irradiation targets and methods of using the same to generate radioisotopes. Example embodiment tie plate attachments may include a plurality of retention bores that permit irradiation targets to be contained in the retention bores. Irradiation targets may be irradiated in an operating nuclear core including the fuel assemblies, generating radioisotopes that may be harvested from the spent nuclear fuel assembly by removing example embodiment tie plate attachments.

Abstract: Target windows for isotope production systems are provided. One target window includes a plurality of foil members in a stacked arrangement. The foil members have sides, and wherein the side of a least one of the foil members engages the side of at least one of the other foil members. Additionally, at least two of the foil members are formed from different materials.

Abstract: Example embodiments and methods are directed to irradiation target positioning devices and systems that are configurable to permit accurate irradiation of irradiation targets and accurate production of daughter products, including isotopes and radioisotopes, therefrom. These include irradiation target plates having precise loading positions for irradiation targets, where the targets may be maintained in a radiation field. These further include a target plate holder for retaining and positioning the target plates and irradiation targets therein in the radiation field. Example embodiments include materials with known absorption cross-sections for the radiation field to further permit precise, desired levels of exposure in the irradiation targets. Example methods configure irradiation target retention systems to provide for desired amounts of irradiation and daughter product production.

Abstract: Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom.

Abstract: Systems produce desired isotopes through irradiation in nuclear reactor instrumentation tubes and deposit the same in a robust facility for immediate shipping, handling, and/or consumption. Irradiation targets are inserted and removed through inaccessible areas without plant shutdown and placed in the harvesting facility, such as a plurality of sealable and shipping-safe casks and/or canisters. Systems may connect various structures in a sealed manner to avoid release of dangerous or unwanted matter throughout the nuclear plant, and/or systems may also automatically decontaminate materials to be released. Useable casks or canisters can include plural barriers for containment that are temporarily and selectively removable with specially-configured paths inserted therein. Penetrations in the facilities may limit waste or pneumatic gas escape and allow the same to be removed from the systems without over-pressurization or leakage.

Abstract: Example embodiments are directed to apparatuses and methods for producing radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable from nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes.

Abstract: The present invention provides a method for producing Cu67 radioisotope suitable for use in medical applications. The method comprises irradiating a metallic zinc-68 (Zn68) target within a sealed ceramic capsule with a high energy gamma ray beam. After irradiation, the Cu67 is isolated from the Zn68 by any suitable method (e.g. chemical and or physical separation). In a preferred embodiment, the Cu67 is isolated by sublimation of the zinc in a ceramic sublimation tube to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means.

Abstract: A target assembly to produce radioisotopes for the synthesis of radiopharmaceuticals. The target assembly includes a target vessel with a target chamber adapted to receive a target material. A thin cover sheet of particle-permeable material covers the target chamber. In a bombardment process, a high-energy particle beam generated by a cyclotron or particle accelerator strikes the thin cover sheet, whereby at least some of the particles from the particle beam penetrate to the target chamber so as to interact with the target material, altering the nuclear makeup of some of the atoms in the target material to produce radioisotopes.

Abstract: In one embodiment, an irradiation target encapsulation assembly, includes a container, at least one first irradiation target disposed in the container, at least one second irradiation target disposed in the container, and a positioning structure configured to position the first irradiation target closer to an axial center of the container than the second irradiation target.

Abstract: A system for automatic production of radioisotopes includes an irradiation unit connectable to a cyclotron and having an electrolytic cell; a purification unit for purifying the radioisotope formed in the irradiation unit; two conduits for transferring an irradiated and electrodissolved target from the irradiation unit to the purification unit; and a central control unit for controlling both the operating units and the transfer means. The method for producing radioisotopes is such that the target carrier is not dissolved together with the irradiated target.

Abstract: A system and method are provided for reclaiming an enriched radioisotope starting material (14) from a target body (12). The system and method enable reclaiming the starting material in a relatively short time (e.g., several hours) after the target body's bombardment with energetic particles, greatly simplifying the target body's chemical processing, as well as reducing the cost of such processing (e.g., reducing the need for costly long-term storage). Specifically, a chemical protective layer (16) is disposed between a radioisotope starting material (14) and a base material (18) of the target body (12). After the target body is irradiated with a suitable source (e.g., particle accelerator), then the irradiated radioisotope starting material and be removed without removing the base material due to the protection provided by the chemical protective layer.

Abstract: A radioisotope production gas target for producing gas isotopes such as C-11. The radioisotope production gas target includes a target chamber that is in the shape of a hollow cylinder and has a plurality of inner fins protruding from an inner surface thereof along a length thereof, and a body that is shaped of a hollow cylinder enclosing the target chamber, and has a target gas inlet for feeding target gas to a hollow region of the target chamber, a target gas outlet for collecting the target gas after a nuclear reaction occurs, and a first coolant inlet and a first coolant outlet respectively feeding and discharging a coolant flowing along an outer surface of the target chamber, and includes a thin metal sheet in front thereof through which a beam of protons passes.

Abstract: An isotope production target may include an outer diameter wall and an inner diameter wall. An isotope source may be located between the inner diameter wall and the outer diameter wall, and the isotope source may comprise fissile material interspersed with one or more voided regions. A central region may be located within the inner diameter wall, and the central region may be configured to house a neutron thermalization volume.

Abstract: An F-18 production target system having an internal support produces F-18 by means of a nuclear reaction of protons and H218O, and reduces the deformation of thin sheets to thus increase the durability of the thin sheets. The F-18 production target system includes a frame, which has the shape of a cylinder the central portion of which is bored, holds H218O in the central portion, and includes through-holes bored from the central portion to the outer circumference thereof, thin sheets, which are installed on opposite sides of the frame so as to seal the central portion, and a support, which is installed in the central portion so as to prevent the thin sheets from being deformed.

Abstract: A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (m, f) reactions in U-238. The U-238 can be deployed as layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material.

Abstract: Example embodiments and methods are directed to irradiation target retention devices that may be inserted into conventional nuclear fuel rods and assemblies. Example embodiment devices may hold several irradiation targets for irradiation during operation of a nuclear core containing the assemblies and fuel rods having example embodiment irradiation target retention devices. Irradiation targets may substantially convert to useful radioisotopes upon exposure to neutron flux in the operating nuclear core and be removed and harvested from fuel rods after operation.

Abstract: A self-shielding target for isotope production systems is provided. The target includes a body configured to encase a target material and having a passageway for a charged particle beam, and a component within the body, wherein the charged particle beam induces radioactivity in the component. Additionally, at least one portion of the body is formed from a material having a density value greater than a density value of aluminum to shield the component.

Abstract: Example embodiments and methods are directed to irradiation target positioning devices and systems that are configurable to permit accurate irradiation of irradiation targets and accurate production of daughter products, including isotopes and radioisotopes, therefrom. These include irradiation target plates having precise loading positions for irradiation targets, where the targets may be maintained in a radiation field. These further include a target plate holder for retaining and positioning the target plates and irradiation targets therein in the radiation field. Example embodiments include materials with known absorption cross-sections for the radiation field to further permit precise, desired levels of exposure in the irradiation targets. Example methods configure irradiation target retention systems to provide for desired amounts of irradiation and daughter product production.

Abstract: The present invention provides a system and method for a system for accommodating a solid target in an accelerator. The system and method includes a target changer having at least one port for accommodating the solid target, an insert for receiving the solid target in the target changer, a piston for providing a vacuum and a cooling system for the solid target, a cylinder for displacing the piston in one of three positions; and a bracket for securing the insert, piston and cylinder to the target changer.

Abstract: The present invention provides a system and method for a system for accommodating a solid target in an accelerator. The system and method includes a target changer having at least one port for accommodating the solid target, an insert for receiving the solid target in the target changer, a piston for providing a vacuum and a cooling system for the solid target, a cylinder for displacing the piston in one of three positions; and a bracket for securing the insert, piston and cylinder to the target changer.

Abstract: At least one very long lived isotope, such as I-129, and a moderator, such as MgH2, is ground, homogeneously mixed and contained in a target assembly which can be at least one target assembly capable of being accessed and vented. The homogeneous mixture is a target which is irradiated, preferrably by a fast reactor flux, thereby transmuting the at least one isotope to a stable or short lived isotope. Resulting gasses, short lived and stable isotopes have medical and industrial uses and value. The transmuted short lived or stable isotopes do not require long term storage.

Abstract: Provided is an isotope delivery system and a method for irradiating a target and delivering the target to an extraction point. The isotope delivery system may include a cable including at least one target for irradiation, a drive system configured for moving the cable, and a first guide configured to guide the cable for insertion and extraction from a nuclear reactor. The method for irradiating a target and delivering a target may include pushing a cable with an attached target through a first guide and into a nuclear reactor using a drive system, irradiating the target in the nuclear reactor, pulling the cable with the attached irradiated target towards the drive system, pushing the cable with the irradiated target towards a loading/unloading area using the drive system, and placing the irradiated target into a transfer cask, wherein the cable is pulled and pushed by the drive system.