DocumentCode :
3172074
Title :
Physics aspects of the ITER design
Author :
Post, D. ; Borrass, K. ; Callen, J. ; Cohen, S. ; Cordey, J. ; Engelmann, F. ; Fujisawa, N. ; Harrison, Michael ; Hogan, J. ; Hopman, H. ; Igitkhanov, Y. ; Kaiser, T. ; Kardaun, O. ; Kaye, S. ; Krasheninnikov, S. ; Kukushkin, A. ; Mukhovatov, V. ; Nevins,
Author_Institution :
Max-Planck-Inst. fur Plasmaphys., Garching, Germany
fYear :
1991
fDate :
30 Sep-3 Oct 1991
Firstpage :
4
Abstract :
The physics of ITER (International Thermonuclear Experimental Reactor) is based on demonstrated tokamak physics and credible extrapolations of that physics. Assessment of the energy confinement and MHD stability requirements led to the choice of the major plasma parameters of 22 MA for the plasma current, a toroidal field of ~5 T, an aspect ratio of ~3, and an elongation of ~2. Among the major accomplishments of the physics group has been the development of a database and an empirical scaling for L-mode energy confinement and the facilitation of an H-mode database and scaling. The divertor heat loads have been estimated by using experimentally validated models. The thermal and mechanical loads due to off-normal events such as disruptions have been based on analysis of the data from other tokamaks. To achieve the required availability of 10%, the pulse length has been extended by the use of current drive using 75 MW 1.3 MeV neutral beam and 45 MW lower hybrid systems. A relatively complete set of plasma diagnostics is planned for ITER. Finally, a physics R and D program has been developed
Keywords :
fusion reactor instrumentation; fusion reactor theory and design; plasma heating; plasma toroidal confinement; 1.3 MeV; 45 MW; 75 MW; H-mode database; ITER design; International Thermonuclear Experimental Reactor; L-mode energy confinement; MHD stability; divertor heat loads; energy confinement; lower hybrid systems; mechanical loads; neutral beam; off-normal events; plasma diagnostics; plasma parameters; tokamak physics; Data analysis; Databases; Extrapolation; Inductors; Magnetohydrodynamics; Physics; Plasma confinement; Plasma stability; Thermal loading; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
Type :
conf
DOI :
10.1109/FUSION.1991.218837
Filename :
218837
Link To Document :
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