There is provided a radionuclide manufacturing system, a computer-readable storage medium storing a radionuclide manufacturing program, a radionuclide manufacturing method, and a terminal device for more stably manufacturing a radionuclide.

A radionuclide manufacturing system includes: a heating unit configured to internally house a target holding a radionuclide; a gas supply unit; an adsorption unit configured to adsorb the radionuclide; a solvent supply unit; a storage unit configured to store a predetermined instruction; and a control unit configured to control the heating unit to heat the target at a temperature at which the radionuclide held in the target is allowed to volatilize, to control the gas supply unit to supply the carrier gas to the heating unit in order to transport the radionuclide volatilized in the heating unit to the adsorption unit, and to control the solvent supply unit in order to supply a solvent for eluting the radionuclide adsorbed to the adsorption unit to the adsorption unit based on the instruction.

A method of producing actinium by using liquefied radium can minimize loss of Ra-226 according to the state change of Ac-225 by producing Ac-225 using Ra-226 of a liquefied state, moving the produced Ac-225 in a liquefied state after Ac-225 is produced, and separating and reusing Ac-225, thereby enabling a nuclear reaction process of Ac-225 to be performed. Further, a method of producing actinium by using liquefied radium according to the present disclosure has an effect of enabling safety to be improved by including a radon collection unit which is capable of discharging and isolating radon produced from Ra-226, thereby preventing radiation exposure due to radon.

The disclosure provide an apparatus for producing a nuclide by using a liquid target which can perform the nuclear reaction process and can discharge the radioactive gas such as Radon within the vial. As described above, an apparatus for producing a nuclide by using a liquid target according to the present disclosure can minimize quantitative loss of a reactant by performing the nuclear reaction process using a target of a liquefied state and reusing a liquefied target on which the nuclear reaction process has not been performed, and can improve safety by enabling the radioactive gas generated to be disposed.

A method of separating actinium and/or radium from proton-irradiated thorium metal. The thorium metal is irradiated to produce isotopes including thorium, actinium and/or radium. The resultant product is dissolved in solution and a selective precipitant is used to precipitate a bulk portion of the thorium. The precipitated thorium can be recovered. Chromatography is carried out on the remaining solution to remove residual thorium and to separate the actinium from the radium.

A system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging and delivering the target cell apparatus into a target station apparatus; a target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus; and (iii) the receiving cell apparatus and the dissolution/purification module.

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.

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and/or control patient infusion procedures.

The present invention comprises a method for the generation of .sup.227Th of pharmaceutically tolerable purity comprising i) preparing a generator mixture comprising .sup.227Ac, .sup.227Th and .sup.223Ra; ii) loading said generator mixture onto a strong base anion exchange resin; iii) eluting a mixture of said .sup.223Ra and .sup.227Ac from said strong base anion exchange resin using a first mineral acid in an aqueous solution; iv) eluting .sup.227Th from said strong base anion exchange resin using a second mineral acid in an aqueous solution whereby to generate a first .sup.227Th solution containing contaminant .sup.223Ra and .sup.227Ac; v) loading the first .sup.227Th solution onto a strong acid cation exchange resin; vi) eluting at least a part of the contaminant .sup.223Ra and .sup.227Ac from said strong acid cation exchange resin using a third mineral acid in aqueous solution; and vii) eluting the .sup.227Th from said strong acid cation exchange resin using a first aqueous buffer solution to provide a second .sup.227Th solution.

Purified thorium-227 of pharmaceutical purity and a pharmaceutical composition comprising the same are also provided.

A radioisotope power source is disclosed. In one embodiment, the power source includes a dielectric liquid held within a vessel, a radioisotope material dissolved as an ionic salt within the dielectric liquid thereby forming an ionic salt solution, and a thermal-to-electric power conversion system configured to receive thermal heat generated from the decay of the radioisotope material and to generate electrical power.

A radioisotope power source is disclosed. In one embodiment, the power source includes a dielectric liquid held within a vessel, a radioisotope material dissolved as an ionic salt within the dielectric liquid thereby forming an ionic salt solution, and a thermal-to-electric power conversion system configured to receive thermal heat generated from the decay of the radioisotope material and to generate electrical power.