Enhanced H-mode pedestals with lithium injection in DIII-D

Periods of edge localized mode (ELM)-free H-mode with increased pedestal pressure and width were observed in the DIII-D tokamak when density fluctuations localized to the region near the separatrix were present. Injection of a powder of 45 µm diameter lithium particles increased the duration of the enhanced pedestal phases to up to 350 ms, and also increased the likelihood of a transition to the enhanced phase. Lithium injection at a level sufficient for triggering the extended enhanced phases resulted in significant lithium in the plasma core, but carbon and other higher Z impurities as well as radiated power levels were reduced. Recycling of the working deuterium gas appeared unaffected by this level of lithium injection. The ion scale, kθρs ~ 0.1–0.2, density fluctuations propagated in the electron drift direction with f ~ 80 kHz and occurred in bursts every ~1 ms. The fluctuation bursts correlated with plasma loss resulting in a flattening of the pressure profile in a region near the separatrix. This localized flattening allowed higher overall pedestal pressure at the peeling–ballooning stability limit and higher pressure than expected under the EPED model due to reduction of the pressure gradient below the 'ballooning critical profile'. Reduction of the ion pressure by lithium dilution may contribute to the long ELM-free periods.

[1]  H. Wilson,et al.  MHD stability analysis of ELMs in MAST , 2006 .

[2]  H. Wilson,et al.  Numerical studies of edge localized instabilities in tokamaks , 2002 .

[3]  Lao,et al.  Regime of very high confinement in the boronized DIII-D tokamak. , 1991, Physical review letters.

[4]  R. Budny,et al.  Observations Concerning the Injection of a Lithium Aerosol into the Edge of TFTR Discharges , 2000 .

[5]  Jet Efda Contributors,et al.  H-mode pedestal scaling in DIII-D, ASDEX Upgrade, and JET , 2011 .

[6]  Y. Kamada,et al.  Pedestal stability comparison and ITER pedestal prediction , 2009 .

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

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

[9]  R. Bell,et al.  Edge transport and turbulence reduction with lithium coated plasma facing components in the National Spherical Torus Experiment a) , 2011 .

[10]  K. C. Lee,et al.  Triggered confinement enhancement and pedestal expansion in high-confinement-mode discharges in the national spherical torus experiment. , 2010, Physical review letters.

[11]  J. Manickam,et al.  The relationships between edge localized modes suppression, pedestal profiles and lithium wall coatings in NSTX , 2011 .

[12]  G. Bateman,et al.  The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library , 2004 .

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

[14]  J. Snipes,et al.  Wall conditioning with impurity pellet injection on TFTR , 1992 .

[15]  R. Bell,et al.  Continuous improvement of H-mode discharge performance with progressively increasing lithium coatings in the National Spherical Torus Experiment. , 2011, Physical review letters.

[16]  T. Osborne,et al.  Initial results of the high resolution edge Thomson scattering upgrade at DIII-D. , 2012, Review of Scientific Instruments.

[17]  R. Maingi,et al.  New steady-state quiescent high-confinement plasma in an experimental advanced superconducting tokamak. , 2015, Physical review letters.

[18]  M. Ono,et al.  The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment , 2008 .

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

[20]  L. L. Lao,et al.  H-mode pedestal characteristics, ELMs, and energy confinement in ITER shape discharges on DIII-D , 1997 .

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

[22]  W. H. Meyer,et al.  2D tomography with bolometry in DIII‐Da) , 1995 .

[23]  O. Sauter,et al.  Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime , 1999 .

[24]  R. Miller,et al.  Hot particle stabilization of ballooning modes in tokamaks , 1987 .

[25]  David R. Smith,et al.  Progress in understanding the enhanced pedestal H-mode in NSTX , 2013 .

[26]  Maxim Umansky,et al.  Stability and dynamics of the edge pedestal in the low collisionality regime: physics mechanisms for steady-state ELM-free operation , 2007 .

[27]  O. Sauter,et al.  Erratum: “Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime” [Phys. Plasmas 6, 2834 (1999)] , 2002 .

[28]  T. Osborne,et al.  Quiescent H-mode operation using torque from non-axisymmetric, non-resonant magnetic fields , 2013 .

[29]  R. D. Deranian,et al.  Progress in quantifying the edge physics of the H mode regime in DIII-D , 2000 .

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

[31]  L. Lao,et al.  Edge localized modes and the pedestal: A model based on coupled peeling–ballooning modes , 2002 .

[32]  R. E. Waltz,et al.  ITER predictions using the GYRO verified and experimentally validated trapped gyro-Landau fluid transport model , 2011 .

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

[34]  H. R. Wilson,et al.  A first-principles predictive model of the pedestal height and width: development, testing and ITER optimization with the EPED model , 2011 .

[35]  R. J. Groebner,et al.  Development and validation of a predictive model for the pedestal height , 2008 .

[36]  R. Bell,et al.  Progress in characterization of the pedestal stability and turbulence during the edge-localized-mode cycle on National Spherical Torus Experiment , 2013 .

[37]  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 .

[38]  H. E. St. John,et al.  Transport simulation of negative magnetic shear discharges , 1994 .

[39]  E. Wolfrum,et al.  Velocimetry analysis of type-I edge localized mode precursors in ASDEX Upgrade , 2014 .

[40]  N. Brooks,et al.  Multichord spectroscopy of the DIII-D divertor region , 1992 .

[41]  L. L. Lao,et al.  Confinement and stability of VH-mode discharges in the DIII-D tokamak , 1992 .

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

[44]  H. Koslowski,et al.  MHD stability analysis of small ELM regimes in JET , 2009 .

[45]  R. Fonck,et al.  Enhanced Sensitivity Beam Emission Spectroscopy System for Nonlinear Turbulence Measurements , 2008, 0805.1271.

[46]  L. Zakharov,et al.  Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment , 2009 .

[47]  T. Osborne,et al.  Pedestal density fluctuation dynamics during the inter-ELM cycle in DIII-D a) , 2011 .

[48]  D K Mansfield,et al.  Edge-localized-mode suppression through density-profile modification with lithium-wall coatings in the National Spherical Torus Experiment. , 2009, Physical review letters.

[49]  T. Osborne,et al.  Characterization of peeling–ballooning stability limits on the pedestal , 2004 .

[50]  L. L. Lao,et al.  Separation of β̄p and ℓi in tokamaks of non-circular cross-section , 1985 .

[51]  Wade,et al.  Experimental confirmation of impurity convection driven by the ion-temperature gradient in toroidal plasmas , 2000, Physical review letters.

[52]  D K Mansfield,et al.  Erratum: New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak [Phys. Rev. Lett. 114, 055001 (2015)]. , 2015, Physical review letters.

[53]  R. Fonck,et al.  Wide-field turbulence imaging with beam emission spectroscopy. , 2010, The Review of scientific instruments.

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