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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.
S. A. Slutz, R. A. Vesey, D. L. Hanson, R. B. Campbell, M. E. Cuneo, T. A. Mehlhorn, J. L. Porter
Fusion Science and Technology | Volume 49 | Number 3 | April 2006 | Pages 374-383
Technical Paper | Fast Ignition | dx.doi.org/10.13182/FST06-A1156
Articles are hosted by Taylor and Francis Online.
Pulsed-power machines can deliver large electrical energies to Z-pinches, which efficiently convert this energy into X-rays that can indirectly drive capsule implosions to obtain high-fusion fuel (D-T) densities. Presently, the Z machine generates 1.0 to 1.8 MJ of soft X-rays radiated from various Z-pinch loads. This output should be roughly doubled when Z is upgraded to ZR in 2006, making ZR an excellent machine to compress materials for fast ignition studies. The Z-Beamlet Laser (ZBL) has been installed adjacent to Z and is currently being used for X-ray backlighting. Presently, ZBL delivers up to 2 TW of 2 (526-nm-wavelength) light in pulses up to 1 ns long. Chirped-pulsed amplification is being added to the ZBL, which will increase the power a thousandfold enabling integrated fast ignitor experiments to be performed on the ZR facility beginning in 2007. Numerical simulations and analytic scaling, which have been performed to design such experiments, are presented in this paper.
