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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.
Y. Miura, M. Mori, T. Shoji, H. Matsumoto, K. Kamiya, K. Ida, S. Kasai
Fusion Science and Technology | Volume 49 | Number 2 | February 2006 | Pages 96-121
Technical Paper | JFT-2M Tokamak | dx.doi.org/10.13182/FST06-A1090
Articles are hosted by Taylor and Francis Online.
The flexible mid-sized machine of JFT-2M has contributed to the understanding of the physics of improved confinement and the control of improved discharges using some innovative techniques. The improved confinement modes achieved during additional heating on JFT-2M were H-mode in both divertor and limiter configurations, improved L-mode, counter-neutral-beam injection, and pellet-injected H-mode. These improved modes are characterized by two improvements: (a) H-mode that has sharp density and temperature gradients at the edge and (b) other modes that have peaked density, temperature, and toroidal rotation profiles near the center. The improvement of pellet-injected H-mode achieved by central fueling was a combination of H-mode and core improvement with peaked profiles. The discovery of limiter H-mode had an impact on the physics understanding of H-mode and showed the formation of a transport barrier at a place without discontinuity of the magnetic field line topology. The appearance of edge-localized modes (ELMs) by applying ergodic fields was investigated, and it was clarified that n 4 helical components were effective in producing ELMs. Scrape-off-layer biasing had the effect of compressing neutrals at the divertor region. It would be understood that compressed neutrals at the divertor region might increase banana ion loss through charge exchange and increase the negative radial electric field inside the separatrix. This situation would reduce the H-mode power threshold. High-recycling-steady (HRS) H-mode could be reproducibly obtained by boronization using tri-methyl-boron. It was found that HRS appears at a pedestal collisionality of e* > 1.