DocumentCode :
3169380
Title :
Current drive and heating systems for an ITER hard option
Author :
Lindquist, W. ; Bulmer, R. ; Fenstermacher, M. ; Nevins, W. ; Parker, J. ; Smith, G. ; Wendland, C. ; Williamson, V. ; Cooper, W. ; Wells, R.
Author_Institution :
Lawrence Livermore Nat. Lab., CA, USA
fYear :
1991
fDate :
30 Sep-3 Oct 1991
Firstpage :
919
Abstract :
A conceptual design was developed for a reference current drive and heating system for a HARD (high aspect ratio design) onion for ITER (International Thermonuclear Experimental Reactor). Twelve neutral beam modules, each rated at 1.3 MeV and 9.2 MW, perform plasma heating and current drive. An electron cyclotron system is used for initiating the plasma and for disruption control. An alternate system was defined, comprising a lower hybrid and ion cyclotron system for heating system for heating and current drive, augmented by the same electron cyclotron system proposed for the reference system. The neutral beam modules have been arranged in groups of three, two in a vertical array and one nested to the side. Four groups, and thus four ports, are required. Since a lower hybrid system is not needed for the HARD option, the two ports allocated for lower hybrid system in the CDA (conceptual design activity) are available. Therefore, the number of ports required for current drive and heating for the HARD option is five (4 neutral beams, 1 electron cyclotron) versus six (3 neutral beams, 2 lower hybrid, and 1 electron cyclotron) for the CDA. The neutral beam modules have been configured in sets of three, 2 in a vertical array, which has significantly reduced the overall height of the system
Keywords :
fusion reactor ignition; fusion reactor theory and design; plasma instability; plasma radiofrequency heating; plasma toroidal confinement; CDA; ITER hard option; International Thermonuclear Experimental Reactor; conceptual design; conceptual design activity; current drive; disruption control; electron cyclotron system; heating systems; high aspect ratio design; ion cyclotron system; lower hybrid; neutral beam modules; overall height; plasma heating; ports; reference system; vertical array; Cyclotrons; Electrons; Heating; Inductance; Laboratories; Particle beams; Plasma density; Plasma stability; Plasma temperature; Steady-state;
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.1991.218699
Filename :
218699
Link To Document :
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