Chromatography columns for the purification of eluates from .sup.68Ge/.sup.68Ga generators comprising silica as stationary phase and purification processes that use said columns are described.

A process for the preparation of a carrier-free Ga-68 solution from an irradiated Zn target, systems comprising components used in the process, and compositions comprising Ga-68 prepared by the process. Purification of Ga-68 is carried out by feeding an irradiation target solution comprising Zn-68, Ga-68 and solid target assembly metals into a system comprising three chromatography columns in succession.

Target assembly includes a target body having a production chamber and a beam passage. The target body includes first and second grid sections that are disposed in the beam passage. Each of the first and second grid sections has front and back sides. The back side of the first grid section and the front side of the second grid section abut each other with an interface therebetween. The back side of the second grid section faces the production chamber. The target assembly also includes a foil positioned between the first and second grid sections. Each of the first and second grid sections has interior walls that define grid channels through the first and second grid sections. The particle beam is configured to pass through the grid channels toward the production chamber. The interior walls of the first and second grid sections engage opposite sides of the foil.

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 closed target 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.45-Ti, .sup.52Mn, or .sup.44Sc by ion exchange chromatography. An example solution 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.

The present disclosure relates processes and systems for producing and/or purifying .sup.68Ga from an irradiated substrate of .sup.68Zn. In some embodiments, the process rely on the use two cation-exchange chromatography columns to separate .sup.68Ga from .sup.68Zn and other radionuclides and metallic impurities. The process achieves a high overall yield of .sup.68Ga and a high effective molar activity while being implementable in a time compatible with the short half-life of .sup.68Ga. In additional embodiments, the process is implemented by an automated system.

Gallium-68 generators that are capable of producing gallium-68 from a germanium-68 source material are disclosed. The source material may be a matrix material (e.g., zeolite) in which germanium-68 is isomorphously substituted for central atoms in tetrahedra within the matrix material. Methods for forming gallium-68 generators are also disclosed.

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 rapid isolation of radionuclides (e.g., .sup.68Ga) produced using a cyclotron and methods for recycling of the parent isotope (e.g., .sup.68Zn) are disclosed. In one version of the method, a solution including a radionuclide (e.g., .sup.68Ga) is created from a target including cations (e.g., .sup.68Zn). The solution including the radionuclide is passed through a first column including a sorbent comprising a hydroxamate resin to adsorb the radionuclide on the sorbent, and the radionuclide is eluted off the sorbent. The cations (e.g., .sup.68Zn) are recovered from a recovery solution that has passed through the first column by passing the recovery solution through a second column including a second sorbent comprising a cation exchange resin.

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.

The invention provides a process for the production of gallium radionuclides, comprising irradiating a ceramic zinc phosphate target with a proton beam.