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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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.
Kazuo A. Tanaka, Ryosuke Kodama, Peter A. Norreys
Fusion Science and Technology | Volume 49 | Number 3 | April 2006 | Pages 342-357
Technical Paper | Fast Ignition | dx.doi.org/10.13182/FST06-A1153
Articles are hosted by Taylor and Francis Online.
This paper reviews the important schemes that have been investigated thus far in fast ignition research. Integral experiments for fast ignition research have been conducted utilizing various schemes: (a) double-pulse experiments with two 100-ps pulses injected to a compressed core, (b) gold cone-guided implosion with 100-TW laser pulse heating, and (c) imploded core heated by both a 100-TW and petawatt laser pulses through gold cones. Reviewing these results, several important issues were raised for further development of fast ignition research. The imploded core heated by a petawatt laser through a gold cone showed a 103 D-D neutron increase compared to the one with only the CD shell implosion.
