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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.”
N. A. Uckan, J. Wesley, D. Boucher, J. Galambos, F. Perkins, D. Post, S. Putvinski
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 579-585
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST96-A11963001
Articles are hosted by Taylor and Francis Online.
Physics design guidelines, plasma performance estimates, and sensitivity of performance to changes in physics assumptions are presented for the ITER-EDA Interim Design. The overall ITER device parameters have been derived from the performance goals using physics guidelines based on the physics R&D results. The ITER-EDA design has a single-null divertor configuration (divertor at the bottom) with a nominal plasma current of 21 MA, magnetic field of 5.68 T, major and minor radius of 8.14 m and 2.8 m, and a plasma elongation (at the 95% flux surface) of ~1.6 that produces a nominal fusion power of ~ 1.5 GW for an ignited burn pulse length of ≥1000 s. The assessments have shown that ignition at 1.5 GW of fusion power can be sustained in ITER for 1000 s given present extrapolations of H-mode confinement (τE = 0.85 × τITER93H). helium exhaust (τ*He/τE = 10). representative plasma impurities (nBe/ne = 2%), and beta limit [βN = β(%)/(I/aB) ≤ 2.5]. The provision of 100 MW of auxiliary power, necessary to access to H-mode during the approach to ignition, provides for the possibility of driven burn operations at Q = 15. This enables ITER to fulfill its mission of fusion power (~ 1-1.5 GW) and fluence (~1 MWa/m2) goals if confinement, impurity levels, or operational (density, beta) limits prove to be less favorable than present projections. The power threshold for H-L transition, confinement uncertainties, and operational limits (Greenwald density limit and beta limit) are potential performance limiting issues. Improvement of the helium exhaust (τ*He/τE ≤ 5) and potential operation in reverse-shear mode significantly improve ITER performance.