Microtearing instabilities and electron transport in NSTX By K.L. Wong, S. Kaye, D.R. Mikkelsen, J.A. Krommes, K. Hill, R. Bell, B. Le Blanc, 34 th EPS.

Slides:



Advertisements
Similar presentations
Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Advertisements

Short wavelength ion temperature gradient driven instability in toroidal plasmas Zhe Gao, a) H. Sanuki, b) K. Itoh b) and J. Q. Dong c) a) Department of.
Stellarator in a Box: Understanding ITG turbulence in stellarator geometries G. G. Plunk, IPP Greifswald Collaborators: T. Bird, J. Connor, P. Helander,
Lecture Series in Energetic Particle Physics of Fusion Plasmas Guoyong Fu Princeton Plasma Physics Laboratory Princeton University Princeton, NJ 08543,
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
RFP Workshop, Stockholm 9-11 /10/ 2008 Numerical studies of particle transport mechanisms in RFX-mod low chaos regimes M.Gobbin, L.Marrelli, L.Carraro,
1 Global Gyrokinetic Simulations of Toroidal ETG Mode in Reversed Shear Tokamaks Y. Idomura, S. Tokuda, and Y. Kishimoto Y. Idomura 1), S. Tokuda 1), and.
Some results / ideas on the effect of flows D. Strintzi, C. Angioni, A. Bottino, A.G. Peeters.
The Stability of Internal Transport Barriers to MHD Ballooning Modes and Drift Waves: a Formalism for Low Magnetic Shear and for Velocity Shear The Stability.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
Large-scale structures in gyrofluid ETG/ITG turbulence and ion/electron transport 20 th IAEA Fusion Energy Conference, Vilamoura, Portugal, November.
Intermittent Transport and Relaxation Oscillations of Nonlinear Reduced Models for Fusion Plasmas S. Hamaguchi, 1 K. Takeda, 2 A. Bierwage, 2 S. Tsurimaki,
1 / 12 Association EURATOM-CEA IAEA 20th Fusion Energy Conference presented by Ph. Ghendrih S. Benkadda, P. Beyer M. Bécoulet, G. Falchetto,
Chalmers University of Technology The L-H transition on EAST Jan Weiland and C.S. Liu Chalmers University of Technoloy and EURATOM_VR Association, S
N EOCLASSICAL T OROIDAL A NGULAR M OMENTUM T RANSPORT IN A R OTATING I MPURE P LASMA S. Newton & P. Helander This work was funded jointly by EURATOM and.
Computer simulations of fast frequency sweeping mode in JT-60U and fishbone instability Y. Todo (NIFS) Y. Shiozaki (Graduate Univ. Advanced Studies) K.
Fluid vs Kinetic Models in Fusion Laboratory Plasmas ie Tokamaks Howard Wilson Department of Physics, University of York, Heslington, York.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
Calculations of Gyrokinetic Microturbulence and Transport for NSTX and C-MOD H-modes Martha Redi Princeton Plasma Physics Laboratory Transport Task Force.
Hybrid Simulations of Energetic Particle-driven Instabilities in Toroidal Plasmas Guo-Yong Fu In collaboration with J. Breslau, J. Chen, E. Fredrickson,
TH/7-2 Radial Localization of Alfven Eigenmodes and Zonal Field Generation Z. Lin University of California, Irvine Fusion Simulation Center, Peking University.
Microstability analysis of e-ITBs in high density FTU plasmas 1)Associazione EURATOM-ENEA sulla fusione, C.R. Frascati, C.P , Frascati, Italy.
Challenging problems in kinetic simulation of turbulence and transport in tokamaks Yang Chen Center for Integrated Plasma Studies University of Colorado.
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
HAGIS Code Lynton Appel … on behalf of Simon Pinches and the HAGIS users CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority.
Micro-tearing induced electron transport A.R. Field 1, R.J. Akers 1, D.J. Applegate 1, W. Guttenfelder 2, M.Reshko 3, C.M.Roach 1, R. Scannell 1, M.Valovic.
O. Sauter Effects of plasma shaping on MHD and electron heat conductivity; impact on alpha electron heating O. Sauter for the TCV team Ecole Polytechnique.
The efficient sustainment of a stable, high-β spheromak: modeling By Tom Jarboe, To PSI-Center July 29, 2015.
Lecture Series in Energetic Particle Physics of Fusion Plasmas
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Internal Transport Barriers and Improved Confinement in Tokamaks (Three possible.
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
NSTX High-k Scattering System on NSTX: Status and Plan* H.K. Park 1, W. Lee 1, E. Mazzucato 1, D.R. Smith 1, C.W. Domier 2, W. Horton 3, S. Kaye 1, J.
Global Stability Issues for a Next Step Burning Plasma Experiment UFA Burning Plasma Workshop Austin, Texas December 11, 2000 S. C. Jardin with input from.
Comparison of Ion Thermal Transport From GLF23 and Weiland Models Under ITER Conditions A. H. Kritz 1 Christopher M. Wolfe 1 F. Halpern 1, G. Bateman 1,
Tearing Parity Microturbulent Drift Modes on NSTX Martha Redi NSTX Results Review 9/21/04 W. Dorland, U. Maryland, J. Baumgaertel, U. Washington (SULI)
(National Institute for Fusion Science, Japan)
1Peter de Vries – ITBs and Rotational Shear – 18 February 2010 – Oxford Plasma Theory Group P.C. de Vries JET-EFDA Culham Science Centre Abingdon OX14.
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
Lecture Series in Energetic Particle Physics of Fusion Plasmas Guoyong Fu Princeton Plasma Physics Laboratory Princeton University Princeton, NJ 08543,
A discussion of tokamak transport through numerical visualization C.S. Chang.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
Modelling the Neoclassical Tearing Mode
Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 6. Neoclassical particle and heat transport Random walk model, diffusion coefficient, particle.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
Neoclassical Effects in the Theory of Magnetic Islands: Neoclassical Tearing Modes and more A. Smolyakov* University of Saskatchewan, Saskatoon, Canada,
21st IAEA Fusion Energy Conf. Chengdu, China, Oct.16-21, /17 Gyrokinetic Theory and Simulation of Zonal Flows and Turbulence in Helical Systems T.-H.
Magnetic fluctuations and electron transport in a spherical toakmak By K.L. Wong In collaboration with R. Bell, S. Kaye, B. Le Blanc, D. Mikkelsen Plasma.
Helically Symmetry Configuration Evidence for Alfvénic Fluctuations in Quasi-Helically Symmetric HSX Plasmas C. Deng and D.L. Brower, University of California,
1 Peter de Vries – ITPA T meeting Culham – March 2010 P.C. de Vries 1,2, T.W. Versloot 1, A. Salmi 3, M-D. Hua 4, D.H. Howell 2, C. Giroud 2, V. Parail.
Simulations of Energetic Particle Modes In Spherical Torus G.Y. Fu, J. Breslau, J. Chen, E. Fredrickson, S. Jardin, W. Park Princeton Plasma Physics Laboratory.
Nonlinear Simulations of Energetic Particle-driven Modes in Tokamaks Guoyong Fu Princeton Plasma Physics Laboratory Princeton, NJ, USA In collaboration.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
Energetic Particles Interaction with the Non-resonant Internal Kink in Spherical Tokamaks Feng Wang*, G.Y. Fu**, J.A. Breslau**, E.D. Fredrickson**, J.Y.
Gyrokinetic Calculations of Microturbulence and Transport for NSTX and Alcator C-MOD H-modes Martha Redi Princeton Plasma Physics Laboratory NSTX Physics.
TH/7-1Multi-phase Simulation of Alfvén Eigenmodes and Fast Ion Distribution Flattening in DIII-D Experiment Y. Todo (NIFS, SOKENDAI) M. A. Van Zeeland.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
An overview of turbulent transport in tokamaks
Numerical investigation of H-mode threshold power by using LH transition models 8th Meeting of the ITPA Confinement Database & Modeling Topical Group.
8th IAEA Technical Meeting on
Influence of energetic ions on neoclassical tearing modes
Yasuhiro Suzuki for the LHD experiment group
T. Morisaki1,3 and the LHD Experiment Group
Validation of theory based transport models
Non-Local Effects on Pedestal Kinetic Ballooning Mode Stability
(TH/8-1, Jae-Min Kwon et al
Stabilization of m/n=1/1 fishbone by ECRH
T. Morisaki1,3 and the LHD Experiment Group
H. Nakano1,3, S. Murakami5, K. Ida1,3, M. Yoshinuma1,3, S. Ohdachi1,3,
Presentation transcript:

Microtearing instabilities and electron transport in NSTX By K.L. Wong, S. Kaye, D.R. Mikkelsen, J.A. Krommes, K. Hill, R. Bell, B. Le Blanc, 34 th EPS Conference on Plasma Physics Warsaw, Poland, July 2-6, 2007 NSTX

Outline ________________________________________ Introduction Properties of microtearing modes Calculation of unstable microtearing modes for NSTX experimental data Theoretical electron thermal conductivity due to microtearing instabilities in NSTX Comparison with TRANSP analysis Reversed magnetic shear plasma Summary NSTX

Introduction ____________________________________ _ Anomalous electron transport is an old subject, almost as old as magnetic fusion research itself While ETG turbulence is a possible candidate for the explanation in tokamaks, here for NSTX, we investigate the stochastic magnetic field effects from microtearing instabilities 1,2 1. M.H. Redi et al., EPS (2003) 2. D.J. Applegate et al.,Plasma Phys.(2004) NSTX

Why is it important for NSTX ? ___________________________________________ Microtearing modes are thought to be important only at the edge of conventional tokamaks like D-III 1 and C-MOD 2 They are stable in the interior of a tokamak where T e is high enough such that ei <  *e They can be the most unstable mode in the interior of NSTX 3, and should saturate at high amplitude due to the low magnetic field 4 1.N. Ohyabu et al., Phys. Rev. Lett. 58, 120 (1987) 2.J. Kesner & S. Migliuolo, Nucl. Fusion 39, 163 (1999) 3.M.H. Redi et al., EPS(2003) 4.J.F. Drake et al., Phys. Rev. Lett. 44, 994 (1980) NSTX

Properties of microtearing modes ____________________________________ _ High-m tearing modes (k || =0) Driven by T e gradient -  ’ is actually negative at high m (stabilizing) Perturbed electric field  E r has odd parity, elongated along B - different from the even parity for ITG modes Propagate in the electron drift direction (GS2:  <0) - opposite to the ITG mode Perturbed magnetic field  B r has even parity and creates magnetic islands at q=m/n In slab geometry, instability requires (a)  e =dlnT e /dlnn e >0.3 (b) Electron Coulomb collision rate e >  *e NSTX

Microtearing modes in toroidal geometry __________________________________________________ In toroidal geometry, trapped particle effects come into play: (1) L. Chen (1977) - collisional detrapping is destabilizing - Krook e (2) Catto (1981) - Lorentz e This driving term has to compete with stabilizing effects like: (1) Field line bending effect (  ’ ≈ -2k  < 0) (2) Collisional effect of passing electrons (3) Ion orbit effects - stabilizing if dT i /dr < dT e /dr - Cowley (1986) When all stabilizing terms are retained, the trapped electron term is too feeble to drive microtearing instabilities in the interior of a realistic conventional tokamak - J. W. Connor (1990) NSTX

The GS2 gyrokinetic stability code _______________________________________ Initial-value algorithm Flux tube geometry (ballooning limit) Calculate the growth rate and mode structure of the most unstable (fastest growing) eigenmode in a preset range of wavenumber Get input parameters directly from TRANSP output file Ref: M. Kotschenreuther et al., Comp. Phys. Comm. 88, 128 (1995) W. Dorland et al., Phys. Rev. Lett. 85, 5579 (2000) NSTX

Plasma equilibrium for NSTX # at 0.9 s ____________________________________ _ NSTX

Mirnov coil signal spectrum __________________________________________

Plasma Equilibrium ____________________________________________________

Results from GS2 code ____________________________________ _ Microtearing modes can be the most unstable mode in the region r/a = In the region where T e has steep gradient (r/a= ), a broad spectrum of microtearing modes are unstable k   s is in the range of , comparable to ITG modes NSTX

Cautionary Remark _______________________________________ The GS2 code only finds the most unstable mode Microtearing modes may still be unstable at other values of k  s, but they do not appear in the GS2 output because some other modes (usually the ITG) are more unstable ITG and microtearing modes have opposite k , which is reflected in the opposite signs of their real frequency NSTX

Benchmark to analytic results __________________________________________ Plasma parameters taken from TRANSP#116313A11, 0.9 s (NBI, H-mode)  e > 0.3 in the region 0.35 <  < 0.75 Choose  = 0.5 where: n e =6.5e13 cm -3, T e =650 ev, L Te =42 cm, L ne =78 cm, B=5 kG, T i =800 ev, e >  *e is satisfied when microtearing modes are unstable according to the GS2 code NSTX

Instability depends on ei __________________________________________________

Nonlinear saturation ____________________________________ _ While the GEM code is still being developed, we rely on exiting nonlinear theory. The nonlinear term causes an energy flow from short (unstable) to long wavelength modes which are stable. Growth and damping rates balance at  B/B ≈  e /L T, and low magnetic field implies large  e and high  B/B. Ref: J. F. Drake et al., Phys. Rev. Lett. 44, 994 (1980) NSTX

Overlapping resistive layers _________________________________________ Resistive layers overlap when m > m o = q(2q’  s ) -1/2 or k>k o For shot A11 at 0.9 s :  s =(2T e /m i ) 1/2 /  ci, B=5kG, a=65cm,  =r/a  q T i T e  s q’=dq/dr m o k o =m o /r _____________________________________________________________________________________ ev 780ev 1.1cm 0.06cm cm * D.A. D’Ippolito et al., Phys. Fluids 23, 771 (1980) NSTX

Global stochastic magnetic field ______________________________________________ When adjacent island chains are separated by KAM surfaces(as electron transport barriers), stochastic field lines are localized near the separatrix When adjacent island chains overlap, global stochastic magnetic field is expected ( usually the KAM surfaces are destroyed before islands overlap - the 2/3 rule ) One can estimate the island width from (  B r ) mn and find that adjacent islands overlap Substantial electron transport should ensue when either adjacent resistive layers or island chains overlap - see D’Ippolito et al.,Phys.Fluids(1980) NSTX

Electron thermal conductivity in stochastic magnetic field ____________________________________ _ When islands overlap, magnetic field lines become stochastic with diffusion coeff D M, the electron thermal conductivity in the collisional regime ( mfp << L c ) can be estimated by :  e = D M v e ( mfp /L c ) where D M ≈ R|  B| 2 /B 2 Ref: A.B. Rechester & Rosenbluth, Phys. Rev. Lett. 40, 38 (1978) T.H. Stix, Nucl. Fusion 18, 353 (1978) B.B. Kadomtsev & O.P. Pogutse (IAEA,Innsbruck-1978) NSTX

Field line correlation length _______________________________________ A rigorous theory 1 on plasma transport in stochastic magnetic fields is extremely complex. The precise formula for the field line correlation length L c is unknown We use L c =qR = field line connection length 2,3 instead of the Kolmogorov-Lyapunov length For NSTX plasmas, the electrons are weakly collisional: 1 < L c / mfp < 10 1.J.A. Krommes et al., J. Plasma Phys. 30, 11 (1983) 2.J.A. Krommes, private communication 3.B.B. Kadomtsev et al., IAEA (1978) NSTX

Comparison between  e exp and  e theo ________________________________________________ Drake’s theory assumes L n >>L T which is not strictly valid in the experiment In the region where L n >L T (  = ), the agreement between  e exp and  e theo is not bad (within a factor 3) In the region  ≤0.4, L n < L T ≥80cm, the driving term from dT e /dr is too weak, and  e may be determined by some other mechanism Get much better agreement (within 40%) in the entire range (  = ) if we replace L T by L where L -1 = L T -1 + L n -1 NSTX

 e due to saturated microtearing modes _________________________________________________ Put  B/B=  e /L T, get  e = (  e /L T ) 2 Rv e (mfp/L c )= (  e /L) 2 v e 2 /( ei q) Use parameters from #116313A11 at 0.9s, L c = qR  Z eff T e n e  e (cm) L n L T (cm) ei (s -1 ) q  e exp  e theo (cm 2 /s) _________________________________________________________________ ev 7.2e e e e5 0.71e

NSTX

Higher T e (0) when microtearing modes are stabilized by reversed magnetic shear _______________________________________________ Growth rate at  =0.3, t=0.32s # normal shear # reversed shear NSTX

Final Remark _________________________________________ NSTX has the flexibility to operate in many regimes. What I show here is just one type of discharge that allows us to study the effect of microtearing modes. There are several ways to improve electron confinement in ST: 1. Raise B T - HHFW heating efficiency improves 2. Raise T e so that e <  *e - can get T e (0) ~ 4 keV by HHFW heating 3. Reversed magnetic shear - High m modes stabilized and T e (0) becomes significantly higher with same NBI power NSTX

Summary ________________________________________ _ Quantitative analysis of anomalous electron transport in NSTX is carried out - use no fudge factor In the entire region of strong T e gradient,  e observed in experiment is in reasonable agreement with nonlinear microtearing mode theory (within 2X), better agreement with grad(n e ) included. This is not surprising because of the low toroidal magnetic field. The high mode amplitude causes global stochastic magnetic field. Microtearing modes are stable in reversed shear plasmas where T e (0) is substantially higher. Existing nonlinear theory can be improved by electromagnetic gyrokinetic simulation (GEM code). NSTX