One embodiment of the present invention relates to a production method of a .sup.226Ra target, a production method of .sup.225Ac, or an electrodeposition solution for producing a .sup.226Ra target, and the production method of a .sup.226Ra target includes an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using an electrodeposition solution that contains .sup.226Ra ions and a pH buffer.

A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants. The uranium is therefore available for reuse, storage, or disposal.

A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants. The uranium is therefore available for reuse, storage, or disposal.

A method of producing enriched .sup.47Sc comprises irradiating a V structure comprising .sup.51V with at least one incident photon beam having an endpoint energy within a range of from about 14 MeV to about 44 MeV to convert at least some of the .sup.51V to .sup.47Sc and form a .sup.47Sc-containing structure. The .sup.47Sc of the .sup.47Sc-containing structure is separated from additional components of the .sup.47Sc-containing structure using a chromatography process. Systems and apparatuses for producing enriched .sup.47Sc are also described.

A method of producing enriched .sup.47Sc comprises irradiating a V structure comprising .sup.51V with at least one incident photon beam having an endpoint energy within a range of from about 14 MeV to about 44 MeV to convert at least some of the .sup.51V to .sup.47Sc and form a .sup.47Sc-containing structure. The .sup.47Sc of the .sup.47Sc-containing structure is separated from additional components of the .sup.47Sc-containing structure using a chromatography process. Systems and apparatuses for producing enriched .sup.47Sc are also described.

Radioisotopes are produced by irradiating enriched stable isotopes in a particle accelerator target assembly with a beam of protons, deuterons, or other charged particles exhibiting sufficient incident energy and current to induce a nuclear reaction. The target assembly receives a recirculating flow of liquid gallium to remove heat flux that would damage the target assembly when operated with high intensity beam currents. The choice of liquid gallium and its eutectic alloys, all liquids at room temperature, over prior art working fluids for the coolant system is advantageous by providing significantly increased heat transfer to prevent target damage, minimizing enriched material losses, thereby decreasing production costs, and realizing greater radioisotope output.

Radioisotopes are produced by irradiating enriched stable isotopes in a particle accelerator target assembly with a beam of protons, deuterons, or other charged particles exhibiting sufficient incident energy and current to induce a nuclear reaction. The target assembly receives a recirculating flow of liquid gallium to remove heat flux that would damage the target assembly when operated with high intensity beam currents. The choice of liquid gallium and its eutectic alloys, all liquids at room temperature, over prior art working fluids for the coolant system is advantageous by providing significantly increased heat transfer to prevent target damage, minimizing enriched material losses, thereby decreasing production costs, and realizing greater radioisotope output.

Disclosed is a target device (10) having a plurality of target material plates (20a, 20b) for producing a radionuclide, lined up in an overlapped manner, configured to produce the radionuclide when a particle beam is irradiated on the target material plates (20a, 20b), the target device (10) having a front plate group (GRF) composed of target material plates (20a) positioned to the front side the particle beam comes in, and a rear plate group (GRR) composed of the target material plates (20b) positioned to the rear side, and the average thickness of the target material plates (20a) composing the front plate group (GRF) being smaller than the average thickness of the target material plates (20b) composing the rear plate group (GRR).

Disclosed is a target device (10) having a plurality of target material plates (20a, 20b) for producing a radionuclide, lined up in an overlapped manner, configured to produce the radionuclide when a particle beam is irradiated on the target material plates (20a, 20b), the target device (10) having a front plate group (GRF) composed of target material plates (20a) positioned to the front side the particle beam comes in, and a rear plate group (GRR) composed of the target material plates (20b) positioned to the rear side, and the average thickness of the target material plates (20a) composing the front plate group (GRF) being smaller than the average thickness of the target material plates (20b) composing the rear plate group (GRR).

A capsule for the transfer of a target material in a conveying system between a target irradiation station and a collecting station comprising: a beamline channel for the passage of an energetic beam irradiating the target material, a target holder holding the target material or a substrate backing the target material at a glancing angle with respect to the beamline channel axis, a degrader foil positioned across the beamline channel for degrading an energy of the energetic beam upstream of the target material, a target cooling inlet and a target cooling outlet for passage of a cooling fluid in a target cooling duct in a vicinity of the target holder such that the target material can be cooled during an irradiation, and a degrader foil cooling inlet and a degrader foil cooling outlet for passage of a cooling gas in a vicinity of the degrader foil.