K. Kuroda, R. Raman, T. Onchi, M. Hasegawa, K. Hanada, M. Ono, B.A. Nelson, J. Rogers, R. Ikezoe, H. Idei, T. Ido, M. Nagata, O. Mitarai, N. Nishino, Y. Otsuka, Y. Zhang, K. Kono, S. Kawasaki, T. Nagata, A. Higashijima, S. Shimabukuro, I. Niiya, I. Sekiya, K. Nakamura, Y. Takase, A. Ejiri, S. Murakami
Nuclear Fusion 64(1) 014002-014002 2023年12月1日
Abstract
Results from the successful solenoid-free plasma startup using the method of transient coaxial helicity injection (transient CHI) in the QUEST spherical tokamak (ST) are reported. Unlike previous applications of CHI on HIT-II and on NSTX which required two toroidal insulating breaks to the vacuum vessel, QUEST uses a first of its kind, floating single biased electrode configuration, which does not use such a vacuum break. Instead, the CHI electrode is simply insulated from the outer lower divertor plate support structure. This configuration is much more suitable for implementation in a fusion reactor than the previous configurations. Transient CHI generated toroidal currents of 135 kA were obtained. The toroidal current during the formation of a closed flux configuration was over 50 kA. These results bode well for the application of transient CHI in a new generation of compact high-field STs and tokamaks in which the space for the central solenoid is very restricted.