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 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.

The invention relates to a phosphate based glass target material, wherein said material comprises an isotopically enriched element or monoisotopic element.

The invention relates to a phosphate based glass target material, wherein said material comprises an isotopically enriched element or monoisotopic element.

A method for generating .sup.44Sc from a target solution, includes the following steps: a step of solid-liquid extraction comprising (a) the precipitation of a target solution comprising metal species with fluoride ions, the target solution comprising at least .sup.44Sc, .sup.44Ti, and .sup.46Sc and other metal impurities, whereby a solution comprising a precipitate made essentially of .sup.46Sc is obtained, and (b) the filtration of the resulting solution and the recovering of the resulting filtrate comprising essentially .sup.44Sc and .sup.44Ti; a step of solid-phase extraction chromatography comprising (c) the loading of the filtrate obtained by the previous step onto a preconditioned hydroxamate column, and (d) the elution of a hydrochloric acid solution through the preconditioned hydroxamate column, and a step of recovering .sup.44Sc from the elution of the previous step.

The present disclosure generally relates to methods and structures for the production of radioisotopes from the thermal neutron irradiation of selected natural isotopes. The methods, structures and operations are applicable to the production of any radioisotope that may be produced from neutron irradiation.

A system and method for automatic production of astatine-211 labeled molecules is described. The invention represents a significant advantage in the preparation of At-211 radiopharmaceuticals including better reproducibility, reduced production time and increased radiation safety. The invention also enables routine automatic synthesis of radiopharmaceuticals in a clinical setting, in conjunction or at short distance from a cyclotron unit capable of producing the radionuclide.

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.

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.

Apparatuses and methods for production of molybdenum targets, and the formed molybdenum targets, used to produce Tc-99m are described. The target includes a copper support plate having a front face and a back face. The copper support plate desirably has dimensions of thickness of about 2.8 mm, a length of about 65 mm and a width of about 30 mm; and the copper support plate desirably has either a circular or an elliptical cavity centrally formed therein by pressing molybdenum powder into the front face with a depth of about 200-400 microns. Also, the copper support plate includes cooling channels dispensed at the back face; wherein the copper support plate is water cooled by a flow of water during irradiation by a proton beam. Molybdenum powder is embedded and compressed onto the cavity of the copper support plate thereby creating a thin layer of molybdenum onto the copper support plate.