Design of ECH launcher for KSTAR advanced Tokamak operation

Joung, Mi; Woo, Minho; Han, Jongwon; Wang, Sonjong; Kim, Sunggug; Hahn, Sanghee; Lee, Dongjea; Kwak, Jonggu; Ellis, Robert

doi:10.1016/j.fusengdes.2019.111395

Design of ECH launcher for KSTAR advanced Tokamak operation

Journal Article · Mon Nov 11 00:00:00 EST 2019 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2019.111395· OSTI ID:1658824

Joung, Mi ^[1]; Woo, Minho ^[1]; Han, Jongwon ^[1]; ^[1]; Kim, Sunggug ^[1]; ^[1]; Lee, Dongjea ^[2]; Kwak, Jonggu ^[1]; Ellis, Robert ^[3]

National Fusion Research Institute, Daejeon (Korea, Republic of)
Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

For the advanced tokamak operation in Korea Superconducting Tokamak Advanced Research (KSTAR), up to 6 MW of electron cyclotron heating (ECH) is planned. The ECH launcher should be able to operate in steady state and serve as a central/off-axis heating and current drive, q-profile control, and control of the neoclassical tearing mode (NTM) and sawtooth. The water cooled launchers have been upgraded to include continuous operation with precise, high-speed real-time control of the beams by integration with the plasma control system (PCS) for supporting the experiments, in particular for suppressing NTM. Here, the launcher was successfully operated for 78 s with about 650 kW EC power, where the temperature of the coolant, with a flow rate of 9.6 lpm, is saturated and approximately 2 °C. The launcher control system had a maximum control cycle of 5 kHz and a motor latency of about 10 ms, and the poloidal scanning speed of the beam was 20 °/s. Additionally, for the higher localization of power deposition, the curvature and size of the mirrors in the launcher were optimized. This paper presents the ECH launcher design and its control system with the operation results.

Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE

OSTI ID:: 1658824

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 151; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (12)

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Modification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas Hong, Joohwan; Henderson, S. S.; Kim, Kimin Nuclear Fusion, Vol. 57, Issue 3 https://doi.org/10.1088/1741-4326/aa5333	journal	February 2017
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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Advanced tokamak operation
ECH
KSTAR
Launcher
Launcher control

Design of ECH launcher for KSTAR advanced Tokamak operation

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References (12)

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