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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.
C. Gormezano, C. D. Challis, E. Joffrin, X. Litaudon, A. C. C. Sips
Fusion Science and Technology | Volume 53 | Number 4 | May 2008 | Pages 958-988
Technical Paper | Special Issue on Joint European Torus (jet) | dx.doi.org/10.13182/FST08-A1744
Articles are hosted by Taylor and Francis Online.
A review of the development of advanced tokamak scenarios at the Joint European Torus (JET) is presented. It has been established that the current profile plays an important role in these regimes, and the presentation of the experimental achievement has been organized with this in mind. The main achievements are discussed: from high beta plasmas starting with a fully diffused plasma current; from hybrid scenarios with a flat current profile and central q around unity; from pellet-enhanced modes where the role of reversed magnetic shear (transiently) was first established; from optimized shear configurations with weakly reversed shear allowing the establishment of internal transport barriers in D-T plasmas for the first time, including the production of 8.2 MW of fusion power; and from strongly reversed shear and steady-state scenarios. The required development of the control techniques for these advanced scenarios is also described. The results obtained have significantly contributed to the development of advanced scenarios for ITER operation. The prospects for further development of hybrid and steady-state scenarios for ITER are indicated in view of the ongoing upgrades to additional heating systems in JET.
