RMP ELM suppression in DIII-D plasmas with ITER similar shapes and collisionalities

Large Type-I edge localized modes (ELMs) are completely eliminated with small n = 3 resonant magnetic perturbations (RMP) in low average triangularity, , plasmas and in ITER similar shaped (ISS) plasmas, , with ITER relevant collisionalities . Significant differences in the RMP requirements and in the properties of the ELM suppressed plasmas are found when comparing the two triangularities. In ISS plasmas, the current required to suppress ELMs is approximately 25% higher than in low average triangularity plasmas. It is also found that the width of the resonant q95 window required for ELM suppression is smaller in ISS plasmas than in low average triangularity plasmas. An analysis of the positions and widths of resonant magnetic islands across the pedestal region, in the absence of resonant field screening or a self-consistent plasma response, indicates that differences in the shape of the q profile may explain the need for higher RMP coil currents during ELM suppression in ISS plasmas. Changes in the pedestal profiles are compared for each plasma shape as well as with changes in the injected neutral beam power and the RMP amplitude. Implications of these results are discussed in terms of requirements for optimal ELM control coil designs and for establishing the physics basis needed in order to scale this approach to future burning plasma devices such as ITER.

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

[2]  D. J. Campbell,et al.  Chapter 1: Overview and summary , 1999 .

[3]  J. L. Luxon,et al.  A design retrospective of the DIII-D tokamak , 2002 .

[4]  E. Doyle,et al.  ELM suppression in low edge collisionality H-mode discharges using n = 3 magnetic perturbations , 2005 .

[5]  J. Scoville,et al.  MULTI-MODE ERROR FIELD CORRECTION ON THE DIII-D TOKAMAK , 2002 .

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

[7]  E. W. Herold,et al.  Controlled fusion , 1959, IRE Transactions on Electron Devices.

[8]  T. L. Rhodes,et al.  Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas , 2005 .

[9]  T. Osborne,et al.  PEDESTAL, SOL AND DIVERTOR PLASMA PROPERTIES IN DIII-D RMP ELM-SUPPRESSED DISCHARGES AT ITER-RELEVANT EDGE COLLISIONALITY , 2007 .

[10]  E. Doyle,et al.  The physics of edge resonant magnetic perturbations in hot tokamak plasmasa) , 2006 .

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

[12]  T. Petrie,et al.  ELM particle and energy transport in the SOL and divertor of DIII-D , 2003 .

[13]  R. Fitzpatrick Bifurcated states of a rotating tokamak plasma in the presence of a static error-field , 1998 .

[14]  K. Burrell,et al.  Edge-localized mode dynamics and transport in the scrape-off layer of the DIII-D tokamak , 2005 .

[15]  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.

[16]  M. Sugihara,et al.  Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER , 2003 .

[17]  Jeffrey H. Harris,et al.  Edge localized mode control with an edge resonant magnetic perturbation , 2005 .