Status of KSTAR electron cyclotron heating system
SCIE
SCOPUS
- Title
- Status of KSTAR electron cyclotron heating system
- Authors
- Bae, YS; Na, YS; Oh, YK; Kwon, M; Bak, JS; Lee, GS; Jeong, JH; Park, SI; Cho, MH; Namkung, W; Ellis, RA; Park, H; Sakamoto, K; Takahashi, K; Yamamoto, T
- Date Issued
- 2007-08
- Publisher
- AMER NUCLEAR SOCIETY
- Abstract
- An 84-GHz, 500-kW electron cyclotron (EC) heating (ECH) system is under installation for ECH-assisted start-up in the Korea Superconducting Tokamak Advanced Research (KSTAR) facility. An 84-GHz, 500-kW gyrotron, and 1.5-MVA power supply system have been installed at KSTAR, and the initial test of the gyrotron has been carried out with a short-pulse condition of 20 As and maximum beam parameters of 80 kV and 25 A that generate an output radio-frequency (rf) power of 500 kW. The planned 2-s-long operation with 500-kW rf output power is beginning with a long-pulse test of the gyrotron power supply. The launcher system was fabricated in collaboration with Princeton Plasma Physics Laboratory. It will inject 500-kW rf power into the KSTAR plasma with a highly flexible steering mirror system, allowing toroidal and poloidal beam deposition scans. KSTAR will employ 170-GHz EC current drive (CD) in ITER-relevant experiments such as the suppression of the neoclassical tearing modes and the creation of an electron internal transport barrier. The Japan Atomic Energy Agency will provide a 170-GHz, I-MW gyrotron on loan in 2008 in accordance with a Korea-Japan fusion collaboration agreement, and it will be used for the 170-GHz, 1-MW ECCD system in 2010. This paper describes the current status of the installation and initial conditioning tests of the 84-GHz gyrotron system as well as the development plan of the 170-GHz ECH and CD system. Also, this paper discusses the CD efficiency and the steering range of the second-harmonic X-mode injection at 170 GHz and 5 MW from an equatorial launcher.
- Keywords
- KSTAR; ECH; preionization; IMPROVED H-MODE; START-UP; ASDEX UPGRADE; CURRENT DRIVE; DIII-D; TOKAMAK; PREIONIZATION; PLASMAS; POWER; ITER
- URI
- https://oasis.postech.ac.kr/handle/2014.oak/31446
- DOI
- 10.13182/FST07-A1510
- ISSN
- 1536-1055
- Article Type
- Article
- Citation
- FUSION SCIENCE AND TECHNOLOGY, vol. 52, no. 2, page. 321 - 333, 2007-08
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