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Fusion Science and Technology
Researchers report fastest purification of astatine-211 needed for targeted cancer therapy
Astatine-211 recovery from bismuth metal using a chromatography system. Unlike bismuth, astatine-211 forms chemical bonds with ketones.
In a recent study, Texas A&M University researchers have described a new process to purify astatine-211, a promising radioactive isotope for targeted cancer treatment. Unlike other elaborate purification methods, their technique can extract astatine-211 from bismuth in minutes rather than hours, which can greatly reduce the time between production and delivery to the patient.
“Astatine-211 is currently under evaluation as a cancer therapeutic in clinical trials. But the problem is that the supply chain for this element is very limited because only a few places worldwide can make it,” said Jonathan Burns, research scientist in the Texas A&M Engineering Experiment Station’s Nuclear Engineering and Science Center. “Texas A&M University is one of a handful of places in the world that can make astatine-211, and we have delineated a rapid astatine-211 separation process that increases the usable quantity of this isotope for research and therapeutic purposes.”
The researchers added that this separation method will bring Texas A&M one step closer to being able to provide astatine-211 for distribution through the Department of Energy’s Isotope Program’s National Isotope Development Center as part of the University Isotope Network.
Details on the chemical reaction to purify astatine-211 are in the journal Separation and Purification Technology.
Fusion Science and Technology | Volume 49 | Number 2 | February 2006 | Pages 215-233
Technical Paper | Plasma and Fusion Energy Physics - Edge Physics and Exhaust | dx.doi.org/10.13182/FST06-A1121
Articles are hosted by Taylor and Francis Online.
Basic properties of the plasma edge in magnetically confined fusion plasmas are summarized. Starting from the magnetic topology of tokamaks we describe the transport of the scrape-off layer including drifts, the transition to high recycling and detached plasma regimes typical for divertors and the consequences of the electrostatic Debye sheath in front of the plasma facing components. The transport of the fuel neutrals (hydrogen atoms and molecules) is described and the concept of power exhaust from line radiation of impurities at the plasma edge is introduced.