Enhanced understanding of non-axisymmetric intrinsic and controlled field impacts in tokamaks

An extensive study of intrinsic and controlled non-axisymmetric field (δB) impacts in KSTAR has enhanced the understanding about non-axisymmetric field physics and its implications, in particular, on resonant magnetic perturbation (RMP) physics and power threshold (P th) for L–H transition. The n = 1 intrinsic non-axisymmetric field in KSTAR was measured to remain as low as δB/B 0 ~ 4 × 10−5 even at high-beta plasmas (β N ~ 2), which corresponds to approximately 20% below the targeted ITER tolerance level. As for the RMP edge-localized-modes (ELM) control, robust n = 1 RMP ELM-crash-suppression has been not only sustained for more than ~90 τ E, but also confirmed to be compatible with rotating RMP. An optimal window of radial position of lower X-point (i.e. R x = m) proved to be quite critical to reach full n = 1 RMP-driven ELM-crash-suppression, while a constraint of the safety factor could be relaxed (q 95 = 5 0.25). A more encouraging finding was that even when R x cannot be positioned in the optimal window, another systematic scan in the vicinity of the previously optimal R x allows for a new optimal window with relatively small variations of plasma parameters. Also, we have addressed the importance of optimal phasing (i.e. toroidal phase difference between adjacent rows) for n = 1 RMP-driven ELM control, consistent with an ideal plasma response modeling which could predict phasing-dependent ELM suppression windows. In support of ITER RMP study, intentionally misaligned RMPs have been found to be quite effective during ELM-mitigation stage in lowering the peaks of divertor heat flux, as well as in broadening the 'wet' areas. Besides, a systematic survey of P th dependence on non-axisymmetric field has revealed the potential limit of the merit of low intrinsic non-axisymmetry. Considering that the ITER RMP coils are composed of 3-rows, just like in KSTAR, further 3D physics study in KSTAR is expected to help us minimize the uncertainties of the ITER RMP coils, as well as establish an optimal 3D configuration for ITER and future reactors.

[1]  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.

[2]  A. Boozer,et al.  Computation of three-dimensional tokamak and spherical torus equilibria , 2007 .

[3]  H. L. Yang,et al.  Design features of the KSTAR in-vessel control coils , 2009 .

[4]  T. Osborne,et al.  L–H transition studies on DIII-D to determine H-mode access for operational scenarios in ITER , 2010 .

[5]  J. G. Bak,et al.  Versatile controllability of non-axisymmetric magnetic perturbations in KSTAR experiments , 2015 .

[6]  J. Park,et al.  Three-dimensional drift kinetic response of high-β plasmas in the DIII-D tokamak. , 2015, Physical review letters.

[7]  Tomonori Takizuka,et al.  Power requirement for accessing the H-mode in ITER , 2008 .

[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]  A. Hyatt,et al.  Tokamak operation with safety factor q95 < 2 via control of MHD stability. , 2014, Physical review letters.

[10]  A. Boozer Error field amplification and rotation damping in tokamak plasmas. , 2001, Physical review letters.

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

[12]  Jae-Min Kwon,et al.  Nonlinear Interaction of Edge-Localized Modes and Turbulent Eddies in Toroidal Plasma under n=1 Magnetic Perturbation. , 2016, Physical review letters.

[13]  The limits and challenges of error field correction for ITERa) , 2012 .

[14]  T. Tala,et al.  Rotation Braking and Error Field Correction of the Test Blanket Module Induced Magnetic Field Error in ITER , 2012 .

[15]  S. G. Lee,et al.  Effects of neoclassical toroidal viscosity induced by the intrinsic error fields and toroidal field ripple on the toroidal rotation in tokamaks , 2016 .

[16]  S. Haskey,et al.  Observation of a multimode plasma response and its relationship to density pumpout and edge-localized mode suppression. , 2015, Physical review letters.

[17]  L. L. Lao,et al.  ELMs and constraints on the H-mode pedestal: peeling–ballooning stability calculation and comparison with experiment , 2004 .

[18]  S. G. Lee,et al.  Suppression of edge localized modes in high-confinement KSTAR plasmas by nonaxisymmetric magnetic perturbations. , 2012, Physical review letters.

[19]  C. Domier,et al.  Two-dimensional imaging of edge-localized modes in KSTAR plasmas unperturbed and perturbed by n=1 external magnetic fields , 2012 .

[20]  Jong-Kyu Park,et al.  Control of asymmetric magnetic perturbations in tokamaks. , 2007, Physical review letters.

[21]  G. A. Navratil,et al.  Stability and control of resistive wall modes in high beta, low rotation DIII-D plasmas , 2007, Nuclear Fusion.

[22]  J. Manickam,et al.  Chapter 3: MHD stability, operational limits and disruptions , 2007 .

[23]  A. Boozer Control of Nonaxisymmetric Magnetic Field Perturbations in Tokamaks , 2011 .