A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, including a target elevator assembly including a body portion defining a central bore and an open bottom end, a center tube that is disposed within the central bore of the body portion, a target basket that is slidably receivable within the center tube, and a winch that is connected to the target basket by a cable, wherein the target basket is configured to receive the radioisotope target therein and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target.

Methods of producing and isolating .sup.68Ga, .sup.89Zr, .sup.64Cu, .sup.63Zn, .sup.86Y, .sup.61Cu, .sup.99mTc, .sup.45Ti, .sup.13N, .sup.52Mn, or .sup.44Sc and solution targets for use in the methods are disclosed. The methods of producing .sup.68Ga, .sup.89Zr, .sup.64Cu, .sup.63Zn, .sup.86Y, .sup.61Cu, .sup.99mTc, .sup.45Ti, .sup.13N, .sup.52Mn, or .sup.44Sc include irradiating a closed target system with a proton beam. The system can include a solution target. The methods of producing isolated .sup.68Ga, .sup.89Zr, .sup.64Cu, .sup.63Zn, .sup.86Y, .sup.61Cu, .sup.99mTc, .sup.45Ti, .sup.52Mn, or .sup.44Sc further include isolating .sup.68Ga, .sup.89Zr, .sup.64Cu, .sup.63Zn, .sup.86Y, .sup.61Cu, .sup.99mTc, .sup.45Ti, .sup.52Mn, or .sup.44Sc by ion exchange chromatography. An example target includes a target body including a target cavity for receiving the target material; a housing defining a passageway for directing a particle beam at the target cavity; a target window for covering an opening of the target cavity; and a coolant gas flow path disposed in the passageway upstream of the target window.

A generator column assembly for the elution of a radioisotope, having a generator column container having a bottom wall defining a flow outlet aperture, an open top end, and a sidewall extending from the open top end to the bottom wall that defines an interior volume having a substantially cylindrical upper volume portion and a substantially cylindrical lower volume portion, the upper volume portion having a diameter that is greater than a diameter of the lower volume portion, and a closure cap assembly including a substantially cylindrical container cap defining a flow inlet aperture, the container cap being configured to be slidably received in the open top end of the generator column container.

A system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging, and delivering. the target cell apparatus into a target station apparatus target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus, and (iii) the receiving cell apparatus and the dissolution/purification module.

A method for separating a parent isotope from a daughter isotope is provided, the method comprising supplying irradiated target; dissolving the irradiated target; treating the dissolved irradiated target to a precipitation step to form a first solid phase of the parent isotope and a first liquid phase of the daughter isotope; filtering the first liquid phase of daughter isotope to create a first purified fraction of the daughter isotope to create a second solid phase of the parent isotope and a second liquid phase of the daughter isotope; and filtering the second liquid phase to create a second liquid fraction of the daughter isotope. The process can be repeated until the .sup.99Mo is exhausted and the enriched target material .sup.98Mo or .sup.100Mo can be easily re-used.

Disclosed are new configurations of a rubidium elution system that offer several advantages. The rubidium elution systems of the present disclosure comprise an assembly including a .sup.82Sr/.sup.82Rb generator, an activity detector, a waste container, a pump, a sensor, a tubing circuit, at least one valve, where the waste container is located in the lower section of the assembly. More particularly, the top surface of the waste container compartment is either below the top surface of the generator compartment, or the waste container is at the same elevation than the generator or below the pump.

Disclosed herein are rubidium elution systems comprising a primary assembly including a .sup.82Sr/.sup.82Rb generator, an activity detector, a waste container, a pump system, a sensor, a tubing circuit, at least one valve, and a computer; and a dose calibrator outside the primary assembly. The system may have an interface for configuring the dose calibrator, and a locking means for preventing access to the interface and reconfigurations of its parameters. Moreover, the dose calibrator may be in electronic communication with the computer of the system. Furthermore, the electronic communication can be embodied with an electronic cable having a breakaway connector. Also, the dose calibrator may be positioned on a mobile platform.

Disclosed herein are methods preparing a purified, carrier-free 68Ga solution. Tire present disclosure also provides systems for preparing a purified, carrier-free 68Ga solution. The present disclosure also provides compositions comprising the purified, carrier-free 68Ga solutions disclosed herein. Also provided are methods of administering compositions of the present disclosure to a patient in need thereof, for example, for imaging a disease or disorder, such as cancer.

Methods for purifying .sup.89Zr are provided, .sup.89Zr compositions are provided, isotope compositions are provided that can include: a radio isotope and a nanoparticle, and methods for radio labeling monoclonal antibodies are provided.

Infusion system configurations and assemblies facilitate routing of infusion circuit tubing lines. Tubing lines are routed into and out from compartments of a shielding assembly for the infusion system, at locations which prevent kinking and/or crushing of the lines, and/or provide for ease in assembling the circuit. A plurality of the lines may be held together by a support frame to form a disposable infusion circuit subassembly, that can further facilitate routing of the lines.