EAST accomplishments/plans in support of fusion next-steps

The Experimental Advanced Superconducting Tokamak (EAST) is a superconducting tokamak, which successfully achieved the first plasma discharging in 2006. The major radius of EAST plasma is 1.9m, and its central magnet filed is 3.5T. In the past few years, EAST has made many achievements such as 60s double-null divertor configuration plasma and 1MA plasma. In 2012, 411s long-pulse discharging with 0.28MA plasma current and 32s H-mode operation were achieved at the seventh campaign. In addition, a new cycle state and fast response of sawtooth with ICRF power modulation were observed. The experimental results and engineering experience got from EAST can be used as a reference for fusion next-step. In order to make further progress, much optimization work should be done in next step. Based on the present EAST heating system, two sets of 4MW neutron beam injection (NBI), one set of electron cyclotron resonance heating (ECRH) and lower hybrid current drive (LHCD) will be installed to achieve more than 30MW total heating power. The upper divertor will be updated to W-Cu divertor which consists of monoblock structure and tungsten armor that can withstand 10 MW·m^-2 heat load. To increase the upper divertor´s ash removal efficiency one new cryo-pump will be added on the behind of it. Aiming to improve plasma configuration and enhance its stabilization, the EAST resonant magnetic perturbation (RMP) coils will be designed. The RMP coils will integrate the functions of error field correction, edge localized mode and resistive wall mode. About forty five kinds of diagnostics will be used in the next campaign and all of them will be integrated on six ports as port plug. And some fusion technologies are also considered in EAST to validate for ITER and future reactor.