Experimental advanced superconducting tokamak

Zonal flow triggers the L-H transition in the Experimental Advanced Superconducting Tokamak

Superconducting Tokamak P. Manz, G. S. Xu, B. N. Wan, H. Q. Wang, H. Y. Guo, I. Cziegler, N. Fedorczak, C. Holland, S. H. Müller, S. C. Thakur, M. Xu, K. Miki, P. H. Diamond, and G. R. Tynan Center for Momentum Transport and Flow Organization, University of California at San Diego, San Diego, California 92093, USA Center for Energy Research, University of California at San Diego, San Diego, Cal...

Influence of helium puff on divertor asymmetry in Experimental Advanced Superconducting Tokamak

Design calculations for fast plasma position control in Korea Superconducting Tokamak Advanced Research

We present the results of fast time scale plasma control simulations for the proposed Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak. Here, the fast plasma control includes stabilization of the vertical instability and rapid radial position control. As a simulation tool, we use the tokamak simulation code (TSC). We evaluate the power supply requirements for both the vertical an...

First observation of a new zonal-flow cycle state in the H-mode transport barrier of the experimental advanced superconducting Tokamak

barrier of the experimental advanced superconducting Tokamak G. S. Xu, H. Q. Wang, B. N. Wan, H. Y. Guo, V. Naulin, P. H. Diamond, G. R. Tynan, M. Xu, N. Yan, W. Zhang, J. F. Chang, L. Wang, R. Chen, S. C. Liu, S. Y. Ding, L. M. Shao, H. Xiong, and H. L. Zhao Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China Association Euratom-Ris! DTU, DK-4000 Roskilde, Denmark Uni...

The ARIES-AT advanced tokamak, Advanced technology fusion power plant

The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive and competitive fusion power in order to guide fusion R&D. The 1000-MWe ARIES-AT design has a major radius of 5.2 m, a minor radius of 1.3 m, a tor...