Curium US LLC

Mallinckrodt, Inc.

Mallinckrodt Nuclear Medicine LLC

William Claude Uhland

David Wayne Pipes

Lauren Radford

Craig Brunkhorst

Brian Regna

Melissa Dianne Perrigo

Arend Booij

Marjolijn Gerritsen

Mark Owens

Shaun Loveless

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.

Purification process for the preparation of non-carrier added copper-64

Disclosed herein are a system and method for electroplating an alpha emitting radionuclide, such as an actinide, for use in alpha spectroscopy. The electrodeposition system for electroplating an alpha emitting radionuclide can include an electroplating cell containing a solution of an electrolyte and the alpha emitting radionuclide, a metal target within the electroplating cell, and a metal anode at a distance from the metal target. The system also includes a platform for supporting the electroplating cell, coupling mechanism connected to the platform, an electric motor on the elastic cushion, and a flywheel with an uneven weight distribution operatively connected to the electric motor. Rotation of the unevenly distributed flywheel generates a vibration in the electroplating cell which dislodges gas bubbles that have formed between the metal target and the metal anode.

Systems and methods for electroplating sources for alpha spectroscopy

The present disclosure generally relates to a new process for generating germanium-68 from an irradiated target body. The process includes irradiation of the target body followed by various extraction techniques to generate the germanium-68.

Process of generating germanium

Processes for producing germanium-68 from a gallium target body are disclosed. In some embodiments, germanium-68 and gallium are precipitated to remove metal impurities. Germanium-68 and gallium are re-dissolved and loaded onto an ion exchange column to separate germanium-68 from gallium.

Processes for generating germanium-68 with reduced volatiles

A system and method are provided for reclaiming an enriched radioisotope starting material from a target body. The system and method enable reclaiming the starting material in a relatively short time (e.g., several hours) after the target body's bombardment with energetic particles, greatly simplifying the target body's chemical processing, as well as reducing the cost of such processing (e.g., reducing the need for costly long-term storage). Specifically, a chemical protective layer is disposed between a radioisotope starting material and a base material of the target body. After the target body is irradiated with a suitable source (e.g., particle accelerator), then the irradiated radioisotope starting material can be removed without removing the base material due to the protection provided by the chemical protective layer. The system and method also enable the operator to obtain three different radioisotopes in a single bombardment of the target body, further reducing cost of radioisotope production.

Target bodies and uses thereof in the production of radioisotope materials

A system and method are provided for reclaiming an enriched radioisotope starting material () from a target body (). The system and method enable reclaiming the starting material in a relatively short time (e.g., several hours) after the target body's bombardment with energetic particles, greatly simplifying the target body's chemical processing, as well as reducing the cost of such processing (e.g., reducing the need for costly long-term storage). Specifically, a chemical protective layer () is disposed between a radioisotope starting material () and a base material () of the target body (). After the target body is irradiated with a suitable source (e.g., particle accelerator), then the irradiated radioisotope starting material and be removed without removing the base material due to the protection provided by the chemical protective layer. The system and method also enable the operator to obtain three different radioisotopes in a single bombardment of the target body, further reducing cost of radioisotope production.

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St. Charles, MO, United States of America

William Claude Uhland