An isotope production system, emanation generator, and process are disclosed for production of high-purity radioisotopes. In one implementation example, high-purity Pb-212 and/or Bi-212 isotopes are produced suitable for therapeutic applications. In one embodiment the process includes transporting gaseous radon-220 from a radium-224 bearing generator which provides gas-phase separation of the Rn-220 from the Ra-224 in the generator. Subsequent decay of the captured Rn-220 accumulates high-purity Pb-212 and/or Bi-212 isotopes suitable for direct therapeutic applications. Other high-purity product isotopes may also be prepared.

An apparatus for producing Pb-212. The apparatus comprises an emanation box that comprises an emanation source comprising a porous non-reactive material. The emanation box receives at least one of Th-228 and Ra-224, wherein the at least one of Th-228 and Ra-224 decays to Rn-220 within the emanation box. The apparatus further includes a carrier gas feed coupled to the emanation box. The carrier gas feed directs an inert gas into the emanation box and the inert gas carries the Rn-220 out of the emanation box through a carrier gas exit port of the emanation box. The apparatus also includes one or more Rn-220 targets coupled to the carrier gas exit port. The carrier gas carries the Rn-220 from the emanation box to the one or more Rn-220 targets and the Rn-220 decays into Pb-212 within the one or more Rn-220 targets. The Pb-212 is directed into the Pb-212 collection container.

Methods and systems for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock comprising thorium and uranium with a first acid to form a first solution. The first solution is contacted an ion exchange resin that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin thereby forming a second solution. The second solution is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate. The precipitate is separated from the second solution.

A method for preparing one or more generators with a high radium-228 content from an aqueous solution comprising thorium-232 and radium-228. The generator(s) can be used, in particular, for producing thorium-228, from which radium-224, then lead-212 and bismuth-212 can be obtained. The method and the generator(s) that it can be used to prepare are therefore applicable, in particular, in the manufacture of radiopharmaceuticals made from lead-212 or bismuth-212, which can be used in nuclear medicine and, in particular, in targeted alpha radiotherapy for the treatment of cancers.

A method for recovering a parent radionuclide from a radionuclide generator is disclosed where the parent radionuclide is adsorbed to a stationary phase. The method contains a series of elutions. At least one elution is with an alcohol. At least one elution with water. At least one elution is with a mineral acid other than hydrochloric acid that is paused to soak the stationary phase with the mineral acid.

A radioisotope elution system is provided. The radioisotope elution system may comprise a controller that is configured to calculate the available amount of daughter radioisotope at any time during establishment of the equilibrium for decay of the parent radioisotope into its daughter radioisotope. The radioisotope elution system may comprise a controller that is configured to schedule various patient infusions planned for the next following days and weeks in accordance with the available amount of daughter radioisotope on each day. The elution system may also comprise a controller that is connected to the imaging software of a radioisotope imaging device, where the radioisotope imaging device is arranged for imaging the patient or a region of the patient; and the controller is configured to start an image acquisition at a predetermined time.

A closure includes a body extending longitudinally along a central longitudinal axis from a first, upper surface to a second, lower surface. The body defines a cavity extending into the body from the lower surface to a third, interior surface. The cavity is sized and shaped to receive a portion of a container therein. The body includes a shroud extending from the interior surface to the lower surface, and a container insert depending from the interior surface and positioned within the cavity. The container insert is sized and shaped to fit within an opening of the container. The body further includes an outlet flow path in fluid communication with the cavity, and at least one inlet flow path in fluid communication with the cavity. The at least one inlet flow path is positioned and oriented to generate a vortex gas flow within the container when connected thereto.

A method for producing .sup.225Ac solution includes steps (I) to (III): a step (I) of passing a solution containing .sup.226Ra and .sup.225Ac through a solid-phase extraction agent (a) that contains a compound represented by formula (A) so as to cause the solid-phase extraction agent (a) to retain .sup.225Ac; a step (II) of passing a liquid containing an eluate, which is obtained by eluting the retained .sup.225Ac from the solid-phase extraction agent (a), through a solid-phase extraction agent (b) that contains a compound represented by formula (B) so as to cause the solid-phase extraction agent (b) to retain .sup.225Ac; and a step (III) of eluting the retained .sup.225Ac from the solid-phase extraction agent (b) to obtain an .sup.225Ac solution.

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A nuclear medicine infusion system (10) may be used to generate and infuse radioactive liquid into a patient undergoing a diagnostic imaging procedure. In some examples, the infusion system includes a frame (30) that carries a radioisotope generator (52) that generates radioactive eluate via elution. The frame may also carry a beta detector (58) and a gamma detector (60). The beta detector can be positioned to measure beta emissions emitted from the radioactive eluate supplied by the generator. The gamma detector can be positioned to measure gamma emissions emitted from a portion of the radioactive eluate to evaluate a safety of the radioactive eluate delivered by the infusion system.

Methods for setting up, maintaining and operating a radiopharmaceutical infusion system, that includes a radioisotope generator, are facilitated by a computer of the system. The computer may include pre-programmed instructions and a computer interface, for interaction with a user of the system, for example, in order to track contained volumes of eluant and/or eluate, and/or to track time from completion of an elution performed by the system, and/or to calculate one or more system and/or injection parameters for quality control, and/or to perform purges of the system, and/or to facilitate diagnostic imaging.