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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.
S. W. Haan, D. A. Callahan, M. J. Edwards, B. A. Hammel, D. D. Ho, O. S. Jones, J. D. Lindl, B. J. MacGowan, M. M. Marinak, D. H. Munro, S. M. Pollaine, J. D. Salmonson, B. K. Spears, L. J. Suter
Fusion Science and Technology | Volume 55 | Number 3 | April 2009 | Pages 227-232
Technical Paper | Eighteenth Target Fabrication Specialists' Meeting | dx.doi.org/10.13182/FST08-3501
Articles are hosted by Taylor and Francis Online.
Targets intended to produce ignition on the National Ignition Facility are being simulated, and the simulations are used to set specifications for target fabrication. Recent design work has focused on refining designs that use 1.3 MJ of laser energy, with an ablator of Be(Cu) or CH(Ge). The mainline hohlraum design now has a He-H gas fill and a wall of U-Au layers. The emphasis in this paper is on changes in the requirements over the last year. Complete tables of specifications are regularly updated for all of the targets. All the specifications are rolled together into an error budget indicating adequate margin for ignition with all of the designs.