A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak

A high-confinement plasma that is potentially useful for controlled fusion has now been sustained for over 30 s. The Experimental Advanced Superconducting Tokamak in Hefei, China, achieved this record pulse length by first confining the plasma using lithium-treated vessel walls, and then maintaining it with a so-called lower hybrid current drive.

[1]  Shunsuke Ide,et al.  Overview of JT-60U progress towards steady-state advanced tokamak , 2005 .

[2]  J. Timberlake,et al.  A Simple Apparatus for the Injection of Lithium Aerosol into the Scrape-Off Layer of Fusion Research Devices , 2010 .

[3]  Ichiko Fuyuno China set to make fusion history , 2006, Nature.

[4]  W. Treutterer,et al.  Type II ELMy H modes on ASDEX Upgrade with good confinement at high density , 2001 .

[5]  J. Melo,et al.  Overview and summary , 1985 .

[6]  W. Kerner,et al.  High fusion performance from deuterium-tritium plasmas in JET , 1999 .

[7]  D. N. Hill,et al.  A review of ELMs in divertor tokamaks , 1997 .

[8]  Shuichi Takamura,et al.  Chapter 4: Power and particle control , 2007 .

[9]  Keith H. Burrell,et al.  Edge stability and transport control with resonant magnetic perturbations in collisionless tokamak plasmas , 2006 .

[10]  K. Spatschek,et al.  Aspects of three dimensional transport for ELM control experiments in ITER-similar shape plasmas at low collisionality in DIII-D , 2008 .

[11]  R. J. Hawryluk,et al.  Results from deuterium-tritium tokamak confinement experiments , 1997 .

[12]  L. Zakharov,et al.  Comparison of various wall conditionings on the reduction of H content and particle recycling in EAST , 2011 .

[13]  M. Becoulet,et al.  Resonant magnetic perturbation experiments on MAST using external and internal coils for ELM control , 2010 .

[14]  T. Fujita,et al.  Chapter 2: Plasma confinement and transport , 2007 .

[15]  H. Zohm Edge localized modes (ELMs) , 1996 .

[16]  J. R. Martin-Solis,et al.  Plasma detachment in JET Mark I divertor experiments , 1998 .

[17]  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.

[18]  T. Pütterich,et al.  First EMC3-Eirene simulations of the impact of the edge magnetic perturbations at ASDEX Upgrade compared with the experiment , 2012 .

[19]  A. Hubbard,et al.  Comparison of small ELM characteristics and regimes in Alcator C-Mod, MAST and NSTX , 2011 .

[20]  J. Ferreira,et al.  Impact of lithium-coated walls on plasma performance in the TJ-II stellarator , 2009 .

[21]  A. Loarte,et al.  Improved performance of ELMy H-modes at high density by plasma shaping in JET , 2002 .

[22]  P. Stangeby The Plasma Boundary of Magnetic Fusion Devices , 2000 .

[23]  Martin Jakobi,et al.  Steady state advanced scenarios at ASDEX Upgrade , 2002 .

[24]  M. L. Apicella,et al.  First experiments with lithium limiter on FTU , 2007 .

[25]  F. Wagner,et al.  Regime of Improved Confinement and High Beta in Neutral-Beam-Heated Divertor Discharges of the ASDEX Tokamak , 1982 .

[26]  A. Polevoi,et al.  Chapter 1: Overview and summary , 2007 .

[27]  R. L. Miller,et al.  Magnetohydrodynamic stability of tokamak edge plasmas , 1998 .

[28]  E. Tsitrone Key plasma wall interaction issues towards steady state operation , 2007 .

[29]  L. Lao,et al.  Plasma shaping, edge ballooning stability and ELM behaviour in DIII-D , 1990 .

[30]  P T Lang,et al.  First observation of edge localized modes mitigation with resonant and nonresonant magnetic perturbations in ASDEX Upgrade. , 2011, Physical review letters.

[31]  A. Loarte Chaos cuts ELMs down to size , 2006 .

[32]  A. Polevoi,et al.  Progress in the ITER Physics Basis - Chapter 1: Overview and summary , 2007 .

[33]  A. Becoulet,et al.  Recent fully non-inductive operation results in Tore Supra with 6?min, 1?GJ plasma discharges , 2004 .

[34]  T. Eich,et al.  Inter-ELM power decay length for JET and ASDEX upgrade: measurement and comparison with heuristic drift-based model. , 2011, Physical review letters.

[35]  Robert J. Goldston,et al.  Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks , 2011 .

[36]  B. Wan,et al.  Recent progress in RF heating and long-pulse experiments on EAST , 2011 .

[37]  Baonian Wan,et al.  Recent experiments in the EAST and HT-7 superconducting tokamaks , 2009 .

[38]  J. Manickam,et al.  The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus Experiment , 2012 .

[39]  N Hawkes,et al.  Active control of type-I edge-localized modes with n=1 perturbation fields in the JET tokamak. , 2007, Physical review letters.

[40]  Dennis Normile,et al.  Waiting for ITER, Fusion Jocks Look EAST , 2006, Science.

[41]  Yuanxi Wan,et al.  Overview of steady state operation of HT-7 and present status of the HT-7U project , 2000 .

[42]  L. Zakharov,et al.  Enhanced energy confinement and performance in a low-recycling tokamak. , 2006, Physical review letters.