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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.
U. Samm
Fusion Science and Technology | Volume 53 | Number 2 | February 2008 | Pages 223-228
Technical Paper | Edge Physics and Plasma-Wall Interactions | dx.doi.org/10.13182/FST08-A1708
Articles are hosted by Taylor and Francis Online.
The control of wall loads in fusion devices, in particular with respect to the life time limitations of wall components due to material erosion and migration, will be decisive for the realisation of a fusion power plant operating in steady state, while in a pulsed experiment like ITER the primary goal for plasma-wall interaction is the achievement of a high availability. The article describes the grand challenges of plasma-wall interaction research along the needs for ITER and the strategies of ongoing research for further optimization of the design. Addressed are questions related to material problems, erosion- and transport processes, tritium retention in deposited layers and transient heat loads.
