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.

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.

A process for producing a daughter radionuclide from a parent radionuclide includes a) loading the parent radionuclide on a first solid medium contained in a generator and onto which the parent radionuclide is retained and whereby the daughter radionuclide is formed by radioactive decay of the parent radionuclide; b) eluting this medium with a A0 solution so as to recover a A1 solution comprising the daughter radionuclide; c) optionally adjusting the pH of the A1 solution so as to obtain a A1 solution, d) loading this A1 or A1 solution onto the head of a second solid medium contained in a chromatography column; e) first washing said second solid medium with a A2 solution; f) second washing said second solid medium with a A2 solution; g) eluting the daughter radionuclide with a A3 solution. The first washing step is conducted from head to tail of the column and the second washing step and the second eluting step are conducted from tail to head of the column.

An infusion system may include a strontium-rubidium 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 determine an activity of rubidium in the radioactive eluate based on the beta emissions measured by the beta detector and determine an activity of strontium in the radioactive eluate based on the gamma emissions measured by the gamma detector.

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 radioisotope elution system is provided, that has at least a component comprised in a cabinet and accessible via a door equipped with an authentication system to ensure safety. The system may also have a user interface equipped with an authentication system. It is also provided a radioisotope elution system that has a dose calibrator equipped with a lifting mechanism for lifting and/or lowering the vial to be tested in the dose calibrator. Advantageously, the lifting mechanism may be controlled for preventing the vial from being lifted during a quality control test on a sample of eluate in the vial. This feature prevents a user from tampering and/or interfering with the vial while a quality control testing is in progress. In another feature, there is provided a radioisotope elution system with a scanning system for entering information about the radioisotope generator and/or the patient in the system. Systems ensuring that the eluant reservoir contains a saline solution are proposed.

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.

The present invention relates to calibration and normalization systems and methods for ensuring the quality of radiopharmaceuticals during the synthesis thereof, such as radiopharmaceuticals used in Positron Emission Tomography (PET) and Single-Photon Emission Computed Tomography (SPECT).

A device for preparing radioactive solutions, in particular radiopharmaceutical solutions, including: a movable support block with at least two cells capable of accommodating a vial; and a shielded covering, including a side wall surrounding the periphery of the support block and an upper wall covering the upper face of the support block, an opening being provided in the upper wall of the covering. A means for driving the support block is configured to selectively displace the support block into positions, referred to as working positions, in which a given cell is aligned with the opening to allow access to the cell from the outside of the covering. The support block is configured such that it can be further brought to a position, referred to as closing position, in which the opening is sealed by a shielded element carried by the support block.