Overview of EAST experiments on the development of high-performance steady-state scenario

The EAST research program aims to demonstrate steady-state long-pulse advanced high-performance H-mode operations with ITER-like poloidal configuration and RF-dominated heating schemes. Since the 2014 IAEA FEC, EAST has been upgraded with all ITER-relevant auxiliary heating and current drive systems, enabling the investigation of plasma profile control by the coupling/integration of various auxiliary heating combinations. Fully non-inductive steady-state H-mode plasma (H98,y2  >  1.1) was extended over 60 s for the first time with sole RF heating plus good power coupling and impurity and particle control. By means of the 4.6 GHz and 2.45 GHz LHCD systems, H-mode can be obtained and maintained at relatively high density, even up to ne ~ 4.5  ×  1019 m−3, where a current drive effect is still observed. Significant progress has been achieved on EAST, including: (i) demonstration of a steady-state scenario (fully non-inductive with Vloop ~ 0.0 V at high βP ~ 1.8 and high-performance in upper single-null (ε ~ 1.6) configuration with the tungsten divertor; (ii) discovery of a stationary H-mode regime with no/small ELM using 4.6 GHz LHCD, and; (iii) achievement of ELM suppression in slowly rotating H-mode plasma with n  =  1 and 2 RMP compatible with long-pulse operations. The new advances in scenario development provide an integrated solution in achieving long-pulse steady-state operations on EAST.

[1]  Youwen Sun,et al.  Evidence and modeling of 3D divertor footprint induced by lower hybrid waves on EAST with tungsten divertor operations , 2017 .

[2]  Ling Zhang,et al.  Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak , 2017 .

[3]  L. L. Lao,et al.  Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST , 2017 .

[4]  Y. Feng,et al.  EMC3-EIRENE Simulations for the Impact of External Magnetic Perturbations on EAST Edge Plasma , 2017 .

[5]  L. L. Lao,et al.  EAST equilibrium current profile reconstruction using polarimeter-interferometer internal measurement constraints , 2017 .

[6]  Liang Wang,et al.  Edge localized mode control using n  =  1 resonant magnetic perturbation in the EAST tokamak , 2017 .

[7]  W. Heidbrink,et al.  Validation of fast-ion D-alpha spectrum measurements during EAST neutral-beam heated plasmas. , 2016, The Review of scientific instruments.

[8]  X. Ji,et al.  Nonlinear Transition from Mitigation to Suppression of the Edge Localized Mode with Resonant Magnetic Perturbations in the EAST Tokamak. , 2016, Physical review letters.

[9]  Fukun Liu,et al.  Characteristics of edge pedestals in LHW and NBI heated H-mode plasmas on EAST , 2016 .

[10]  Fukun Liu,et al.  Integrated Operating Scenario to Achieve 100-Second, High Electron Temperature Discharge on EAST ⁄ , 2016 .

[11]  Xu Handong,et al.  Development and Preliminary Commissioning Results of a Long Pulse 140 GHz ECRH System on EAST Tokamak (Invited) , 2016 .

[12]  Naulin,et al.  Comparison of HESEL SOL turbulence simulations with BES measurements on EAST , 2016 .

[13]  M. Goto,et al.  A fast-time-response extreme ultraviolet spectrometer for measurement of impurity line emissions in the Experimental Advanced Superconducting Tokamak. , 2015, The Review of scientific instruments.

[14]  Yahong Xie,et al.  Overview of Development Status for EAST-NBI System , 2015 .

[15]  Yingying Li,et al.  Edge-coherent-mode nature of the small edge localized modes in Experimental Advanced Superconducting Tokamak , 2014 .

[16]  J. Fu,et al.  Preparations for the motional Stark effect diagnostic on EAST. , 2014, The Review of scientific instruments.

[17]  P. Bonoli,et al.  Characterization of the onset of ion cyclotron parametric decay instability of lower hybrid waves in a diverted tokamak , 2014 .

[18]  N. Gorelenkov,et al.  Numerical study of Alfvén eigenmodes in the Experimental Advanced Superconducting Tokamak , 2014 .

[19]  B N Wan,et al.  New edge coherent mode providing continuous transport in long-pulse H-mode plasmas. , 2014, Physical review letters.

[20]  Alessandro Galli,et al.  Spectral broadening of parametric instability in lower hybrid current drive at a high density , 2014 .

[21]  B N Wan,et al.  Magnetic topology changes induced by lower hybrid waves and their profound effect on edge-localized modes in the EAST tokamak. , 2013, Physical review letters.

[22]  Yueqiang Liu,et al.  Full toroidal plasma response to externally applied nonaxisymmetric magnetic fields , 2010 .

[23]  G Schettini,et al.  Current drive at plasma densities required for thermonuclear reactors. , 2010, Nature communications.

[24]  Massimiliano Mattei,et al.  Principal physics developments evaluated in the ITER design review , 2009 .

[25]  D. Reiser,et al.  Plasma currents induced by resonant magnetic field perturbations in tokamaks , 2009 .

[26]  M. Chatelier Integration of high power, long pulse operation in Tore Supra in preparation for ITER , 2007 .

[27]  R. Mitteau,et al.  Key results of long pulse ICRH operation in Tore Supra , 2006 .

[28]  M E Fenstermacher,et al.  Suppression of large edge-localized modes in high-confinement DIII-D plasmas with a stochastic magnetic boundary. , 2004, Physical review letters.

[29]  D. A. Gates,et al.  High β, long pulse, bootstrap sustained scenarios on the National Spherical Torus Experiment (NSTX) , 2003 .

[30]  J. Stober,et al.  Accumulation of impurities in advanced scenarios , 2003 .

[31]  X. Litaudon,et al.  A dimensionless criterion for characterizing internal transport barriers in JET , 2002 .

[32]  L. L. Lao,et al.  LONG-PULSE, HIGH-PERFORMANCE DISCHARGES IN THE DIII-D TOKAMAK , 2000 .

[33]  R. J. Hawryluk,et al.  An Empirical Approach to Tokamak Transport , 1981 .

[34]  John E. Shelton People's Republic of China , 1973 .