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Status of KSTAR electron cyclotron heating system SCIE SCOPUS

Title
Status of KSTAR electron cyclotron heating system
Authors
Bae, YSNa, YSOh, YKKwon, MBak, JSLee, GSJeong, JHPark, SICho, MHNamkung, WEllis, RAPark, HSakamoto, KTakahashi, KYamamoto, 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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조무현CHO, MOO HYUN
Div. of Advanced Nuclear Enginrg
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