Kyushu University Academic Staff Educational and Research Activities Database
List of Presentations
Takumi Onchi Last modified date:2019.06.28

Assistant Professor / Advanced Fusion Research Center / Research Institute for Applied Mechanics


Presentations
1. Takumi Onchi, H. Idei, M. Hasegawa, K. Kuroda, R. Ikezoe, K. Hanada, A. Ejiri, T. Kariya, S. Kubo, T.I. Tsujimura, A. Fukuyama, Second harmonic EC plasma ramp-up through production of energetic electrons on the QUEST spherical tokamak, 60th Annual Meeting of the APS Division of Plasma Physics, 2019.11.
2. T. Onchi, H. Idei, K. Nakamura, T. Nagata, S. Kawasaki, R. Ashida, M. Fukuyama, M. Hasegawa, R. Ikezoe, A. Higashijima, K. Kuroda, Y. Nagashima, and K. Hanada, High voltage electrical system of 8.56 GHz CW klystron for electron cyclotron heating on QUEST spherical tokamak, 30th Symposium on Fusion Technology (SOFT2018), 2018.09, A high voltage DC power supply for the cathode of the 8.56 GHz CW klystron has been set up for electron cyclotron heating (ECH) in steady state tokamak operation on QUEST spherical tokamak. The power supply is equipped with an IGBT array and a reactor for fast shutoff of the voltage in 10 μs, where the influx of electric energy at the short circuit is limited to 5 J. AC switches also have been installed in the three-phase power lines. High voltage relays are useful to save electric energy consumption. Fast three-phase AC switching by IGBT-stack is applicable to reduce the electric load of the components of the klystron power supply..
3. T. Onchi, H. Idei, K. Nakamura, M. Hasegawa, K. Yamasaki, O. Watanabe, K. Mishra, K. Kuroda, A. Kuzmin, H. Ohwada, A. Ejiri, H. Togashi, N. Matsumoto and K. Hanada, Present status of current-drive system in QUEST spherical tokamak, AAPPS-DPP 2017, 2017.09, In the medium size spherical tokamak QUEST, plasma current can be ramped up solely by electron cyclotron heating (ECH). Steady-state tokamak operation (SSTO) for approximately 2 hours was performed with CW 8.2 GHz Klystrons [1]. In short pulse operations using 28 GHz Gyrotron (270 kW), second harmonic EC wave was injected via multi-wall reflection and plasma current reached Ip = 66 kA [2]. Ohmic heating (OH) achieved Ip > 100 kA with high current power supply although electron density is as low as ne < 1018 m-3. For more efficient and effective heating and current-drive, new systems of ECH and OH are under development in QUEST. Co-axial Helicity Injection (CHI) has been also installed recently to start-up plasma current initially.
Present 28 GHz second harmonic ECH system is equipped with two quasi-optical mirrors. EC wave after the wave guide are reflected at the 1st convex mirror. Expanded beam is focused by the 2nd concave mirror in to the resonance position. Size of the focused beam can be about 5 cm diameter. The power density becomes 75 MW/m2 with 150 kW injection power. A pair of polarizers (/4 and /8) has been also installed so that X-mode can be formed and be injected [3]. In EC current drive experiments with such local second harmonic X-mode injection, plasma current reaches Ip > 70 kA with increasing vertical magnetic field in about 1 s discharge, as presented in Fig. 1(a), where electron density in the central region is ne > 1018 m-3 [4]. Inboard-limited configuration is formed in such plasma as shown in Fig.1(b). To achieve SSTO following 28 GHz ECH, a new CW-ECH system is under development. Frequency of the Klystron is 8.56 GHz and the maximum injection power can be 250 kW.
Upgrade of OH system is also in progress. A capacitor bank of C = 55 mF has been refurbished and reinstalled in the system recently. Tokamak configuration with Ip > 70 kA can be obtained more stably owing to the OH system assisted by 28 GHz ECH. As a next step, a unit, consisting of the capacitor bank and two high current power supplies, is designed to drive bipolar primary-current.
Plasma current can be driven by a variety of scenarios with ECH, OH and CHI. A fully non-inductive current drive scenario is applying ECH after CHI. Using 8.56 GHz CW-ECH, SSTO is achievable as long as plasma current is ramped up enough. OH after non-inductive current start-up is also promising. Experiment of electron Bernstein wave would be possible on condition that electron density exceeds the cut-off density and O-X-B mode conversion occurs with 8.56 GHz O-mode injection from low field side. As presented in Fig. 2, higher plasma current than Ip of 100 kA is expected for both short-pulse operation and SSTO in the future scenarios..
4. Takumi Onchi, Hiroshi Idei, Makoto Hasegawa, Hiroaki Ohwada, Hideki Zushi, Kazuaki Hanada, Tsuyoshi Kariya, Kishore Mishra, Taichi Shikama, Quest Team, Non-inductive current built-up by local electron cyclotron heating and current drive with a 28 GHz focused beam on QUEST, 58th Annual Meeting of the APS Division of Plasma Physics, 2016.11.
5. TAKUMI ONCHI, H. IDEI, M.HASEGAWA, T. NAGATA, K. KURODA, K. HANADA, T. KARIYA, S. KUBO, T.I. TSUJIMURA, S. KOBAYASHI, NIFS, QUEST TEAM, Electron cyclotron heating/current-drive system using high power tubes for QUEST spherical tokamak, 59th Annual Meeting of the APS Division of Plasma Physics, 2017.10.