摘要
The Experimental Advanced Superconducting Tokamak （EAST） is the first fully superconducting tokamak with a D-shaped cross-sectional plasma presently in operation. The ideal magnetohydrodynamic （MHD） stability and required power for the EAST advanced tokamak （AT） scenario with negative central shear and double transport barrier （DTB） are investigated. With the equilibrium code TOQ and stability code GATO, the ideal MHD stability is analyzed. It is shown that a moderate ratio of edge transport barriers＇ （ETB） height to internal transport barriers＇ （ITBs） height is beneficial to ideal MHD stability. The normalized beta/3N limit is about 2.20 （without wall） and 3.70 （with ideal wall）. With the scaling law of energy confinement time, the required heating power for EAST AT scenario is calculated. The total heating power Pt increases as the toroidal magnetic field BT or the normalized beta βN is increased.
The Experimental Advanced Superconducting Tokamak （EAST） is the first fully superconducting tokamak with a D-shaped cross-sectional plasma presently in operation. The ideal magnetohydrodynamic （MHD） stability and required power for the EAST advanced tokamak （AT） scenario with negative central shear and double transport barrier （DTB） are investigated. With the equilibrium code TOQ and stability code GATO, the ideal MHD stability is analyzed. It is shown that a moderate ratio of edge transport barriers＇ （ETB） height to internal transport barriers＇ （ITBs） height is beneficial to ideal MHD stability. The normalized beta/3N limit is about 2.20 （without wall） and 3.70 （with ideal wall）. With the scaling law of energy confinement time, the required heating power for EAST AT scenario is calculated. The total heating power Pt increases as the toroidal magnetic field BT or the normalized beta βN is increased.
基金
supported by the National Natural Science Foundation of China (No.10975161)
the Special Project of the Ministry of Science and Technology of China (No.2009GB101001)
