Disclosed herein are rubidium elution systems comprising a primary assembly including a .sup.82Sr/.sup.82Rb generator, an activity detector, a waste container, a pump system, a sensor, a tubing circuit, at least one valve, and a computer; and a dose calibrator outside the primary assembly. The system may have an interface for configuring the dose calibrator, and a locking means for preventing access to the interface and reconfigurations of its parameters. Moreover, the dose calibrator may be in electronic communication with the computer of the system. Furthermore, the electronic communication can be embodied with an electronic cable having a breakaway connector. Also, the dose calibrator may be positioned on a mobile platform.

Infusion system configurations and assemblies facilitate routing of infusion circuit tubing lines. Tubing lines are routed into and out from compartments of a shielding assembly for the infusion system, at locations which prevent kinking and/or crushing of the lines, and/or provide for ease in assembling the circuit. A plurality of the lines may be held together by a support frame to form a disposable infusion circuit subassembly, that can further facilitate routing of the lines.

Gallium-68 generators that are capable of producing gallium-68 from a germanium-68 source material are disclosed. The source material may be a matrix material (e.g., zeolite) in which germanium-68 is isomorphously substituted for central atoms in tetrahedra within the matrix material. Methods for forming gallium-68 generators are also disclosed.

The present invention provides a system for evaporating a radioactive fluid, a method for the synthesis of a radiolabelled compound including this system, and a cassette for the synthesis of a radiolabelled compound comprising this system. The present invention provides advantages over known methods for evaporation of a radioactive fluid as it reduces drastically the amount of radioactive gaseous chemicals that are released in the hot cell. It is gentler and more secure compared to the known process and provides access to radiosyntheic processes that may not been acceptable for safety reasons related to release of volatile radioactive gases during evaporation. In addition, the process yields are higher because the radioactive volatiles are labelled intermediate species.

Certain embodiments of the present invention relate to a system and a method for producing a radiopharmaceutical, wherein the system is formed from and/or provides a microfluidic flow system. In certain embodiments, the system comprises a radioisotope isolation module, a radiopharmaceutical production module, a purification module and a quality control module.

The invention relates to a method for preparing lead (212) for medical use. This method comprises the production of lead (212) by the decay of radium (224) in a generator comprising a solid medium to which the radium (224) is bound, followed by the extraction of the lead (212) from the generator in the form of an aqueous solution A1, characterised in that the lead (212) contained in the aqueous solution A1 is purified from the radiological and chemical impurities, also contained in said aqueous solution, by a liquid chromatography on a column. The invention also relates to an apparatus specially designed for automated implementation in a closed system of said method. It further relates to lead (212) produced by means of this method and this apparatus. Applications: manufacture of radiopharmaceuticals based on lead (212), useful in nuclear medicine for the treatment of cancers, particularly by a-radioimmunotherapy, or for medical imaging, in both humans and animals.

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.

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.

Systems and/or methods for producing free elements, systems and/or methods for producing element storage/generation vessel assemblies, element storage/generation vessel assemblies, system and/or methods for purifying elements and providing a progeny generating assemblies are provided.

Infusion system configurations and assemblies facilitate routing of infusion circuit tubing lines. Tubing lines are routed into and out from compartments of a shielding assembly for the infusion system, at locations which prevent kinking and/or crushing of the lines, and/or provide for ease in assembling the circuit. A plurality of the lines may be held together by a support frame to form a disposable infusion circuit subassembly, that can further facilitate routing of the lines.