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 annular radioisotope target and method therefor that includes an inner cladding tube and a helical coil-shaped foil ribbon disposed over the inner cladding tube. The helical coil-shaped foil ribbon has a first end, a second end, a first edge and a second edge. An outer cladding tube is disposed over the helical coil-shaped foil ribbon and inner cladding tube, and end caps are attached to the outer cladding tube and the inner cladding tube.

An aqueous assembly has a negative coefficient of reactivity with a magnitude. The aqueous assembly includes a vessel and an aqueous solution, with a fissile solute, supported in the vessel. A reactivity stabilizer is disposed within the aqueous solution to reduce the magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly.

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.

The present disclosure provides a composition that includes a mixture of (i) radioactive microparticles; and (ii) non-radioactive microparticles. The radioactive microparticles may be suitable to treat a vascularized tumour, such as a liver tumour or a metastasized liver tumour. The radioactive microparticles and the non-radioactive microparticles may have substantially the same resistance when flowing in a liquid through a conduit. The present disclosure also provides methods of making and methods of using mixtures of microparticles.

A method for producing Pb-212 isotope comprises introducing Th-228 into an emanation box. The emanation box comprises an emanation source comprising a high-surface area material. The method also includes introducing a carrier gas into the emanation box through a carrier gas feed. The method also includes separating the Rn-220 from the carrier gas in the one or more Rn-220 targets, directing the carrier gas out of the one or more Rn-220 targets through a carrier gas exhaust port, directing a liquid through a liquid feed into the one or more Rn-220 targets, and allowing the Rn-220 to undergo radioactive decay into Pb-212 isotope within the one or more Rn-220 targets. The liquid dissolves the Pb-212 isotope produced by radioactive decay of Rn-220 within the one or more Rn-220 targets. The method further includes directing the liquid containing the Pb-212 isotope from the one or more Rn-220 targets to a Pb-212 collection container, and separating the Pb-212 isotope from the liquid.

A method of producing actinium by using liquefied radium includes 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 Ac-225 and reusing Ra-226. As a result, a nuclear reaction process of Ac-225 may be performed and loss of Ra-226 may be minimized. Further, such a method may improve safety 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 present disclosure relates in general to nuclear medicine and generators for the production of radiopharmaceuticals for medical use. In particular, present disclosure relates to a generator column that resists high heat such as depyrogenation and sterilization. This allows some steps of the preparation of the column to be performed in a non-sterile environment. This also allows the generator column to be reusable. The present disclosure further describes methods for the preparation of a generator where a parent radioisotope is charged on the column matrix before or after the matrix is loaded in the column.

A modular radio-labeling tracer synthesizer system comprising a housing having a plurality of slots containing syringe actuators. Each syringe actuator including a syringe holder, a syringe driver for driving a syringe plunger in a loading and/or dispensing direction. The unit is capable of adopting multiple configurations and is fully programmable and provides enhanced flexibility in development of novel radiotracers.

Disclosed are new configurations of a rubidium elution system that offer several advantages. The rubidium elution systems of the present disclosure comprise an assembly including a .sup.82Sr/.sup.82Rb generator, an activity detector, a waste container, a pump, a sensor, a tubing circuit, at least one valve, where the waste container is located in the lower section of the assembly. More particularly, the top surface of the waste container compartment is either below the top surface of the generator compartment, or the waste container is at the same elevation than the generator or below the pump.