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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.”
R. W. Moir, J. D. Lee, M. S. Coops, F. J. Fulton, W. S. Neef, Jr., D. H. Berwald, R. B. Campbell, B. Flanders, J. K. Garner, N. Ghoniem (Consultant, UCLA), J. Ogren, Y. Saito, A. Slomovik, R. H. Whitley, K. R. Schultz, G. E. Benedict, E. T. Cheng, R. L. Creedon I. Maya, V. H. Pierce, J. B. Strand, C. P. C. Wong, J. S. Karbowski, R. P. Rose, J. H. Devan, P. Tortorelli, L. G. Miller, P. Y. S. Hsu, J. M. Beeston, N. J. Hoffman, D. L. Jassby
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 589-598
Fusion System Studies | doi.org/10.13182/FST4-2P2-589
Articles are hosted by Taylor and Francis Online.
Studies of the technical and economic feasibility of producing fissile fuel in tandem mirrors and in tokamaks for use in fission reactors are presented. Fission-suppressed fusion breeders promise unusually good safety features and can provide make-up fuel for 11 to 18 LWRs of equal nuclear power depending on the fuel cycle. The increased revenues from sales of both electricity and fissile material might allow the commercial application of fusion technology significantly earlier than would be possible with electricity production from fusion alone. Fast-fission designs might allow a fusion reactor with a smaller fusion power and a lower Q value to be economical and thus make this application of fusion even earlier. A demonstration reactor with a fusion power of 400 MW could produce 600 kg of fissile material per year at a capacity factor of 50%. The critical issues, for which small scale experiments are either being carried out or planned, are: 1) material compatibility, 2) beryllium feasibility, 3) MHD effects, and 4) pyrochemical reprocessing.