ITER (International Thermonuclear Experimental Reactor) current drive and heating physics

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6413009

Nevins, W M; Lindquist, W ^[1]; Fujisawa, N; Kimura, H ^[2]; Hopman, H; Rebuffi, L; Wegrowe, J G ^[3]; Parail, V; Vdovin, V ^[4]

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1. Lawrence Livermore National Lab., CA (USA)
2. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan)
3. Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.). NET Design Team
4. Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehn

The ITER Current Drive and Heating (CD H) systems are required for: Ionization and current initiation; Non-inductive current ramp-up assist; Heating of the plasma; Steady-state operation with full non-inductive current drive; Current profile control; and Burn control by modulation of the auxiliary power. Steady-state current drive is the most demanding requirement, so this has driven the choice of the ITER current drive and heating systems.

• Research Organization: International Atomic Energy Agency, Vienna (Austria)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6413009
• Report Number(s): IAEA-CN-53/F-3-4; CONF-901025-14; ON: DE91001631; TRN: 90-034378
• Resource Relation: Conference: 13. international conference on plasma physics and controlled nuclear fusion research, Washington, DC (USA), 1-6 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ITER TOKAMAK
ECR HEATING
NON-INDUCTIVE CURRENT DRIVE
IONIZATION
LOWER HYBRID CURRENT DRIVE
CLOSED PLASMA DEVICES
HEATING
HIGH-FREQUENCY HEATING
PLASMA HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production