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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.
A. I. Kislyakov, A. J. H. Donné, L. I. Krupnik, S. S. Medley, M. P. Petrov
Fusion Science and Technology | Volume 53 | Number 2 | February 2008 | Pages 577-603
Technical Paper | Plasma Diagnostics for Magnetic Fusion Research | dx.doi.org/10.13182/FST08-A1680
Articles are hosted by Taylor and Francis Online.
Three techniques for particle diagnostics of magnetically confined fusion plasmas are reviewed: charge exchange neutral particle analysis, Rutherford scattering, and heavy ion beam probes. The physical basis and instrumentation for each technique are described. Typical examples obtained by these diagnostics are presented. Charge exchange analysis is used for ion temperature measurements in small- and medium-sized plasma devices and for the study of the ion energy distribution function, especially in the suprathermal energy range. It also provides an ion isotope composition determination that is a high-priority task for ITER. Rutherford scattering enables local measurements of the ion temperature as well as measurements of the ion collective velocity. The heavy ion beam probe diagnostic gives a unique opportunity to measure locally the electric plasma potential and, by that, the electric field profile in a plasma and its influence on confinement. Other significant options of this diagnostic are the measurements of the local electron density and fluctuations in these quantities. Prospects for the application of the various techniques to ITER are discussed.