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 α ray to bismuth to produce astatine-211 in the bismuth, and a step of distilling the bismuth that received α ray irradiation with a carrier gas containing an inert gas, O.sub.2 and H.sub.2O to separate and purify astatine-211, and dissolving the astatine-211 in a solution.

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.

A method for obtaining .sup.225AC from .sup.225Ra having the steps of assembling a column having an inorganic stationary phase; priming the column to immobilize .sup.226Ra .sup.225Ra and natural decay products therefrom; immobilizing the .sup.226Ra, .sup.225Ra, .sup.224Ra, and natural decay products therefrom onto a stationary phase within the column; and eluting the column containing the .sup.225Ra with an aqueous sulfate solution to obtain a milking effluent that contains .sup.225AC. Also provided is a method for obtaining pure .sup.225AC from its isotope parents, the method comprising assembling a column having a stationary phase comprising an inorganic material; priming the column with the isotope parents to immobilize .sup.225Ac, and natural decay products of .sup.225AC; immobilizing the .sup.225Ac, and natural decay products therefrom onto the stationary phase within the column .sup.226Ra, .sup.225Ra, .sup.224Ra; and eluting the column containing the .sup.225AC to obtain an effluent that contains the isotope parents.

Described are methods and compositions for processes of preparing a radioactive solution of Sn-117m tetraiodide. Aspects include reacting a radioactive solid Sn containing Sn-117m with a solution of I.sub.2 in an organic solvent at a temperature and for a duration sufficient to result in the formation of Sn-117m tetraiodide. Then, the organic solvent is removed by evaporation to leave dry Sn-117m tetraiodide. The organic solvent is a low boiling point solvent capable of dissolving I.sub.2 and Sn tetraiodide. The organic solvent is selected from the group consisting of an alcohol and a chlorinated solvent. In embodiments may be selected from the group consisting of dichloromethane, trichloromethane, tetrachloromethane, or mixtures thereof. In embodiments, the organic solvent excludes alcohol. The I.sub.2 may be in a slight molar excess to the radioactive solid Sn. The method may further include distilling the reactants to remove excess I.sub.2 from the distillate.

An infusion system (10) including a radioisotope generator (52) that generates a radioactive eluate via an elution, an activity detector (58) configured to measure an activity of a first radioisotope in the radioactive eluate generated by the radioisotope generator, and a controller (80). The controller can track a cumulative volume of radioactive eluate generated by the radioisotope generator and also track the activity of the first radioisotope in the radioactive eluate generated by the radioisotope generator. The controller can determine a predicted volume of the radioactive eluate generated by the radioisotope generator at which the activity of the first radioisotope in the radioactive eluate will reach a threshold based on the tracked cumulative volume of the radioactive eluate and the tracked activity of the first radioisotope. This information can be useful for proactively removing the radioisotope generator from service and/or replacing the radioisotope generator with a fresh generator.

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.

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.

A method for producing 225.sup.A including: a method (X) for purifying a .sup.226Ra-containing solution, including an adsorption step of allowing a .sup.226Ra ion to adsorb onto a carrier having a function of selectively adsorbing a divalent cation by bringing a .sup.226Ra-containing solution into contact with the carrier under an alkaline condition, and an elution step of eluting the .sup.226Ra ion from the carrier under an acidic condition; a method for producing a .sup.226Ra target, including an electrodeposition liquid preparation step of preparing an electrodeposition liquid by using a purified .sup.226Ra-containing solution obtained by the method (X), and an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using the electrodeposition liquid; and a step of irradiating a .sup.226Ra target produced by the method for producing a .sup.226Ra target with at least one selected from a charged particle, a photon, and a neutron by using an accelerator.

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.

Described are methods for preparing radionuclides, such as radionuclides having a high specific activity. The disclosed methods include irradiating target nuclide materials, in solution, with a neutron source. The radionuclides can be separated from the target nuclide material by providing a solid carbon nanostructured material, as a suspension of solids, proximal to the target nuclide material in solution and using the recoil to drive adsorption of the radionuclide onto the solid carbon nanostructured material to transfer the radionuclides from the liquid phase (in solution) to the solid phase (adsorbed to the suspended solid carbon nanostructured material). One or more surfactants can be incorporated into the solution to facilitate formation of a stable suspension of the solid carbon nanostructured material.