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ANS Student Conference 2025
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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Terry Kammash
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 227-230
Fusion-Fission Hybrids and Transmutation | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13424
Articles are hosted by Taylor and Francis Online.
A fusion-fission hybrid reactor whose fusion component is the gasdynamic mirror (GDM) is proposed for power production that could meet the world's energy needs of the next several decades. The choice of the GDM is based on the fact that it is linear, axisymmetric and can operate in steady state. Since the primary role of the fusion component is to supply neutrons to the blanket, it can operate at or near “breakeven” condition, a much less stringent condition than that required for a pure fusion reactor. A large aspect ratio GDM is desirable because of MHD stability considerations, and if we choose such a geometry then a cylindrically symmetric plasma with a surrounding blanket can be treated as semi-infinite cylinders, allowing for the reactor performance to be determined by two, one-dimensional equations: one describing the time evolution of the fissile material density bred in the fertile blanket, and another describing the diffusion of fast neutrons in that region. Our choice for the blanket material is thorium-232 in order to take advantage of the thorium fuel cycle that leads to the breeding of uranium-233. Such a fuel cycle is known to be resistant to proliferation and clandestine operations. We choose to operate the GDM at 0.10 of breakeven, using deuterium-tritium (DT) plasma at a density of 1016 cm-3, and a temperature of 10keV. We find that for a reasonable design, such a reactor can generate tens of megawatts of thermal power per cm “safely” because it is “subcritical”, and “securely” because of our choice of the fuel cycle. A systems analysis reveals that about 2% of the net electric power is needed to sustain the fusion component. Moreover, we find that it takes approximately 4 months to reach steady state due to the several steps involved in the breeding cycle.