Search for Suitable ICRF Operation Window for the Shaped H-mode Operation of KSTAR
- National Fusion Research Institute, Gwahangno 113, Yusung-gu, Daejeon 305-333 (Korea, Republic of)
KSTAR will try to achieve its 1st shaped H-mode plasma in 2010 campaign. The available power is limited by our plan for auxiliary heating system. Up to 2010, NBI with 1 MW, LHCD 0.5 MW, and ECH with 0.5 MW power will be prepared. To accomplish high beta plasma, TF magnetic field will be reduced to 2 T from rated field of 3.5 T. In this case the ECH contribution to H-mode power threshold requirement is ignorant because the 84 GHz frequency does not meet neither fundamental nor second harmonic resonance in the discharge area. Therefore the ICRF heating should carry out important roll to reach power threshold. The ICRF system of tunable frequency from 30 to 60 MHz will come with 1 MW power in 2010. To maximize the ICRF heating efficiency for H-mode purpose, we try to find suitable condition of ICRF heating parameters through the simulation using by TORIC code. Optimizations of RF frequency, toroidal modes controllable by 4 current straps, and the minority concentration are performed. Possibilities of second harmonic heating of minority and the mode converted heating near resonance layer are also studied.
- OSTI ID:
- 21335703
- Journal Information:
- AIP Conference Proceedings, Vol. 1187, Issue 1; Conference: 18. topical conference on radio frequency power in plasmas, Gent (Belgium), 24-26 Jun 2009; Other Information: DOI: 10.1063/1.3273725; (c) 2009 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AUXILIARY HEATING
COMPUTERIZED SIMULATION
ECR HEATING
GHZ RANGE
HIGH-BETA PLASMA
H-MODE PLASMA CONFINEMENT
ICR HEATING
LOWER HYBRID CURRENT DRIVE
MAGNETIC FIELDS
MHZ RANGE
OPERATION
PLASMA DENSITY
PLASMA SIMULATION
PLASMA WAVES
TOKAMAK DEVICES
TOROIDAL CONFIGURATION