RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

Size: px
Start display at page:

Download "RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS"

Transcription

1 RESISTIVE WALL MODE STABILIZATION RESEARCH ON STATUS AND RECENT RESULTS by A.M. Garofalo1 in collaboration with J. Bialek,1 M.S. Chance,2 M.S. Chu,3 T.H. Jensen,3 L.C. Johnson,2 R.J. La Haye,3 G.A. Navratil,1 M. Okabayashi,2 J.T. Scoville,3 E.J. Strait,3 and A.D. Turnbull3 1Columbia University, New York, New York. 2Princeton University, Princeton, New Jersey. 3General Atomics, San Diego, California. April 16, 21 Columbia University 77 1/AMG/wj

2 TWO STABILIZATION APPROACHES HAVE BEEN EXPLORED ON Rotational Stabilization Stable window exists when Ω >> Ω c Ω c a few percent of Alfvén transit frequency Growth Rate (γ) τ Α 1 RWM Regime (γ< ) Ideal Kink Regime Magnetic Feedback Stabilization Slow growth time makes feedback practical τ W 1 Increasing Rotation Improves Plasma Surface Wall Radius r c Ideal Kink Limit Originally proposed by Bondeson and D. Ward /jy

3 OUTLINE Rotational stabilization Rotation slowdown above no-wall beta limit 3 Unstable RWM and torque balance 3 Stable RWM and error field amplification Recent experimental results Magnetic feedback stabilization 1-D feedback model and comparison with experimental results 2-D model versus experiment 3-D model versus experiment Recent sensor upgrades and experimental results Summary Future plans 77 1/AMG/wj

4 EARLIER EXPERIMENTS SHOWED PLASMA ROTATION SLOWDOWN AT β N EXCEEDING NO WALL LIMIT 2 dω (ρ~.5) dt (khz/s) H mode ACCELERATION H mode What causes the slowdown? H mode ELMing H mode ELMing ELMing no-wall 1.5 E w = β N /β N DECELERATION 77-1/jy

5 INCREASING NEUTRAL BEAM TORQUE ONLY DELAYS INSTABILITY Rotation threshold shown by varying neutral beam torque Neutral beam torque increased by reducing voltage at constant power Greater torque gives faster initial rotation, identical profiles at transition 3 2 I p β N # of Neutral Beam Sources (15 rad/s) Plasma Toroidal Rotation t=12 ms 1 (gauss) (km/s) n=1 δbr at wall Plasma Toroidal Rotation ρ ~ Time (ms) (15 rad/s) Plasma Toroidal Rotation t=1325 ms t=137 ms ρ 77-1/jy

6 NONLINEAR MODEL ALLOWS SUDDEN CHANGES IN PLASMA ROTATION FREQUENCY AND MODE GROWTH RATES Plasma rotation Ω from torque balance is multivalued (depends on mode rotation) [C. G. Gimblett and R. J. Hastie, Phys. Plasmas 7, 258 (2)] Ω Ω UNSTABLE with slow growth rate (γ «1/τ w ) Growth rate is small (γ << τ 1 ) on the upper branch. Rotation slowly decreases as mode amplitude increases Ω 2 Ω 1 "forbidden" band of plasma rotation UNSTABLE with growth rate γ ~ 1/τ w δb r At the upper knee (if outside the stable window) torque balance is lost, and the rotation frequency drops to the lower branch Growth rate is much larger (γ ~ τ 1 ) on the lower branch Similar to "forbidden" frequency bands for tearing modes [D. Gates and T. Hender, Nucl. Fusion 36, 273 (1996)] Ω = plasma rotation frequency of unperturbed equilibrium 77-1/jy

7 MODEL IS QUALITATIVELY CONSISTENT WITH TRAJECTORY OF WALL-STABILIZED DISCHARGES Evolution at high beta has three phases: Slow mode growth with constant or slowly decreasing plasma rotation More rapid deceleration of rotation as slow mode growth continues Rapid mode growth v φ (km/s) at ρ = SHOT 9782, ms β exceeds β no-wall crit Rotation threshold for RWM in experiment is significantly higher than in Gimblett-Hastie model δb r (G) 77-1/jy

8 DISCOVERY OF ERROR FIELD AMPLIFICATION CAN EXPLAIN PLASMA ROTATION SLOWDOWN ABOVE NO-WALL β LIMIT Merginally stable RWM can be excited to finite amplitude by resonant, un-corrected error field [A.H. Boozer, Phys. Rev. Lett. (21)] Incremental external error field pulsed on and off in discharges with β N well below and close to the no wall limit Larger n=1 plasma response measured at higher β N (Gauss) (km/s) (Gauss) β N B Error Field at q=2 n=1 δb r at Wall (plasma response only) Plasma Toroidal Rotation (ρ~.4) Time (ms) 77-1/jy

9 RATE OF DECAY OF PLASMA ROTATION REDUCED WITH REDUCED ERROR FIELD Previous error correction algorithum obsolete when β N > β N no wall Onset of n=1 RWM delayed to rotation 6 khz at q=2 β N - β N no wall increases with delay of RWM, eventual γτw is larger C Coil79 (A) ROT@q=2 (khz) Reduced static n=1 error field n=1 δb r (gauss) β N Critical Rotation for onset of RWM No wall limit (approx.) Time (ms) 77-1/jy

10 β N MAINTAINED 5% ABOVE CALCULATED n=1 NO-WALL LIMIT FOR ~1.5 SECONDS Error field minimization and increased injected power allow complete, quasi-stationary RWM stabilization Ip (A) β N Plasma Toroidal Rotation (Km/s) Mirnov Amplitude (T/s) n=1 δbr (gauss) P beam (kw) β N no wall ~ 2.4 l i Time (ms) 77-1/jy

11 ERROR CORRECTION WAVEFORMS SUGGESTED BY FEEDBACK USING INTERNAL POLOIDAL FIELD SENSORS ALLOW ROTATIONAL STABILIZATION UP TO β N =2 β N no wall I p (MA) p inj *1 (kw) betan 2.4*l i Ideal limit with wall? 1. Approximate no-wall limit -Eigenvalue (No Wall) Ideal MHD n=1 eigenvalue (~ g 2 ) with no wall.1 Stable eigenvalues Time (ms)

12 BRAKING EXPERIMENT AT DIFFERENT βs GIVES EXPERIMENTAL BENCHMARKING OF CALCULATED NO-WALL LIMIT Error field correction turned off at β N just above and just below the calculated no-wall limit RWM strongly stable below β N no wall -> small error field drag amplification RWM weakly stable with rotation above β N no wall -> large amplification C-coil current (A) β N β N no wall Plasma Toroidal Rotation (km/s) n=1 δbr (gauss) Time (ms) 77-1/jy

13 SAME PHYSICS OF ERROR FIELD-RWM INTERACTION OBSERVED FOR PLASMAS WITH β N NO-WALL ~4li OR ~2.4li C-coil current (A) β N Plasma Toroidal Rotation (km/s) n=1 δbr (gauss) β N no wall ~ 4 l i /jy

14 RWM FEEDBACK EXPERIMENT ON Six midplane coils (C-Coil) Six Sensors } Connected in anti-parallel for n=1 control Three Power supplies dc - 1 Hz, 5 ka Shared with error field correction Vacuum Vessel τ w 5 ms o Sensor Loops Active Coil (C-Coil) x Active Coil (C-Coil) 77-1 jy

15 1-D FEEDBACK MODEL GIVES QUANTITATIVE PREDICTIONS OF FEEDBACK DYNAMICS Symmetry assuption: Toroidal / y = ik ; Poloidal / z = ; φ(x,y) = φ(x)eiky Dispersion relation: 1 - G Cntrl = G f comp G 1 + iωτ f α = iωτw α = 1 G P + G D iωτd G + i 1 + iωτ p 1 + iωτd 1 + iωτi e 2kD 1 e 2kD G = G Cntrl G Hdw G Hdw Ω = 1 Ω1 + i ω x Ω 2 Ω 2 + i Plasma properties described in one number: D = distance from resistive wall at which ideal wall gives marginal stability Wall properties described in one number: τ w = resistive wall time constant Linear electronics Exact modeling of proportional, derivative, integral gains for smart shell, mode control, fake rotating shell, etc. Realistic model of amplifier + coils frequency response function (Ω 1, Ω 2 determined from fit to measurements of the amplifier + coil transfer function) Feedback problem reduced to finding roots of 7th order polynomial with complex coefficients Model successfully benchmarked against experiments ω 77 1/AMG/wj

16 EXPERIMENTAL PARAMETER SCAN SHOWS QUANTITATIVE AGREEMENT WITH 1-D FEEDBACK MODEL 1 2 Diamagnetic Flux (mv s) Gd scan 1415 / 1418 / 1411 G d = 11 G p = 5 G i = G d = 14 G p = 5 G i = 3 No Feedback Time (ms) 155 ω (Rad/s) Derivative gain is stabilizing Gd Scan 14 G p = Stable γ (1/s) Plasma Mode Vacuum Mode Unstable /jy

17 EXPERIMENTAL PARAMETER SCAN SHOWS QUANTITATIVE AGREEMENT WITH 1-D FEEDBACK MODEL 1 2 Diamagnetic Flux (mv s) Gi Scan G d = 14 G p = 5 G i = 31 τ i = 1 ms Gd scan / 1415 / 1418 / 1411 G d = 11 G p = 5 G i = G d = 14 G p = 5 G i = ω (Rad/s) 3 No Feedback Time (ms) Derivative gain is stabilizing Gd Scan 14 G p = Stable γ (1/s) Plasma Mode Vacuum Mode Unstable The integral gain is destabilizing G p = 5, G d = 14 Gi Scan Stable τ i = 1 ms γ (1/s) Unstable /jy

18 EXPERIMENTAL PARAMETER SCAN SHOWS QUANTITATIVE AGREEMENT WITH 1-D FEEDBACK MODEL 1 2 Diamagnetic Flux (mv s) Gi Scan G d = 14 G p = 5 G i = 31 τ i = 1 ms τ i = 1 ms / / 1415 / 1418 / 1411 Gd scan G d = 11 G p = 5 G i = G d = 14 G p = 5 G i = ω (Rad/s) 3 No Feedback Time (ms) Derivative gain is stabilizing Gd Scan 14 G p = Stable γ (1/s) Plasma Mode Vacuum Mode Unstable The integral gain is destabilizing G p = 5, G d = 14 Gi Scan 31 Stable τ i = 1 ms τ i = 1 ms γ (1/s) 31 Unstable /jy

19 COUPLED GATO-VACUUM CODES PREDICT MODE STRUCTURE IS NOT CHANGED SIGNIFICANTLY WITH FEEDBACK Self-consistent 2-D MHD calculation including feedback field Coil Coverage Eddy Pattern on the Wall Without Feedback 1. Internal Radial Displacement on Midplane Without Feedback ξ r With Feedback With Feedback o o Toroidal Direction 36. ρ. 1. With midplane coil only, the total eddy current pattern was not changed significatly Internal mode structure was unchanged, except slightly peaked with feedback 77-1/jy

20 EXPERIMENT SHOWS MODE STRUCTURE OUTSIDE THE WALL IS NOT CHANGED SIGNIFICANTLY WITH/WITHOUT FEEDBACK Toroidal Array Three Toroidal Arrays of Saddle Loops Provide Poloidal Mode Structure Upper Array Midplane Array 1 Lower Array Time (ms) Mode Structure Relative to Midplane θ = θ = Qualitatively consistent with VACUUM/GATO prediction Without Feedback (13353) With Feedback (13353) Relative Toroidal Angle θ = Supports rigid displacement assumption used in lumped parameter formulation and 3D feedback codes 268-/jy

21 VALEN 3D FEEDBACK CONTROL MODEL PREDICTS IMPROVED β LIMIT WITH EXISTING 6 COIL SET Existing 6 coil set can increase RWM stability limit by ~ 2% towards ideal wall β N limit for basic smart shell control algorithm Three control system improvements: shorter sensor coils internal sensor coils internal Bp sensors Base Six-Element C-Coil can reach 5% towards ideal wall beta using internal Bp sensor Growth Rate (s -1 ) No Feedback Base C-Coil 1 4 ideal kink resistive wall mode Short, internal Br sensors Internal Bp sensors β N - β N no-wall β N ideal-wall - β N no-wall ideal wall limit 77-1/jy

22 (G) GATING FEEDBACK OFF DEMONSTRATES STABILIZATION AT β N JUST ABOVE STABILITY BOUNDARY 2 1 Large instability in comparison case without feedback n=1 δb r (G) without Feedback with Feedback β N Time (ms) Feedback Gain Relative Displacement (SXR) (cm) Feedback Current (C79) (ka) with Feedback without Feedback ρ= Time (ms) Rapid RWM growth when feedback is switched off Prompt suppression of RWM when feedback resumes 77-1/jy

23 NEW RWM SENSORS AVAILABLE FOR FY1 FEEDBACK EXPERIMENTS New saddle loops inside the vessel measure the radial field closer to plasma New Mirnov probes increase to 4 the number of diametrically opposed measurements of the poloidal field inside the vessel C Coil External δb r Internal δb r Internal B r Loops o Internal δb p Internal B p Loops External B r Loops C Coil x 325-/AMG/jy

24 PLASMA DISPLACEMENTS DEDUCED FROM X-RAY DATA AGREE WITH MAGNETIC PERTURBATIONS MEASURED BY δb r AND δb p SENSORS X-RAY INTENSITY (arb) º Camera 195º Camera ρ =.29 ρ =.42 ρ =.55 R(195º) R(45º) (cm) ρ =.29 ρ =.42 ρ =.55 #16179 MODE AMPLITUDE (gauss) δb p δb r x TIME (ms) db (gauss) δb p (195º) δb p (45º) [δb r (285º) δb r (135º)] x TIME (ms) 77-1/jy

25 INTERNAL LOOPS ARE MORE EFFECTIVE THAN EXTERNAL LOOPS FOR STABILIZATION OF RWM; CONSISTENT WITH VALEN PREDICTIONS β N *1 NO FEEDBACK Internal B r Loops o 1 n=1 δbr (gauss) External B r Loops C-Coil β N *1 FEEDBACK WITH EXTERNAL SENSOR LOOPS x 2 1 n=1 δbr (gauss) β N *1 FEEDBACK WITH INTERNAL SENSOR LOOPS 2 1 n=1 δbr (gauss) Time (ms) 77-1/jy

26 SUMMARY RWM and plasma rotation Discovery of error field amplification by marginally stable RWM, suggested by theory, provides mechanism for rotation slowdown above no-wall β limit Minimizing error field enables demonstration of rotational stabilization at β N ~ 5% above β N no-wall RWM detection on SXR and magnetics in excellent agreement RWM feedback modeling 1-D feedback simulation code describes feedback system dynamics GATO-VACUUM 2-D codes predict little effect of feedback on plasma eigenfunction VALEN 3-D code used for optimization studies of feedback configurations 3 Predicts large gain in stable beta with internal RWM sensors RWM feedback experiments no-wall Clear demonstration of RWM suppression by feedback for β N just above β N Observation of rigid RWM structure when feedback is applied Comparison of different sensors agrees qualitatively with predictions 77 1/AMG/wj

27 EXTENDED 18 COIL SET CAN INCREASE RWM STABILITY LIMIT TO 8% OF INCREMENTAL PERFORMANCE OF IDEAL WALL Active coil can be extended with 6 coils above and 6 coils below existing C-coil Extended 18-element C-coil can reach 8% towards ideal wall beta limit using internal B p sensors Expanded Coil Set (22) Growth Rate (s 1) Existing six Coils No Feedback Base C-Coil 1 4 Ideal kink 1 Resistive wall mode 18-coil with short, internal B r sensors 18-coil with internal B p sensors Ideal wall limit no-wall β N β N β N ideal-wall no-wall β N 77 1/AMG/wj

28 FUTURE PLANS Short-range plans Explore correction of error field amplification by feedback control Continue comparison of feedback performance with different sensor locations 3 External B r, internal B r, internal B p Quantitative benchmarking of VALEN versus experiment Finalize design of 18-element active coil set Begin integration of RWM control with advanced tokamak scenarios Long-range plans Install C coil extension Compare 6-coil versus 18-coil control system Extend advanced tokamak operating range through RWM control 77 1/AMG/wj

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER GA A24759 RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER by A.M. GAROFALO, J. BIALEK, M.S. CHANCE, M.S. CHU, D.H. EDGELL, G.L. JACKSON, T.H. JENSEN, R.J.

More information

Resistive Wall Mode Control in DIII-D

Resistive Wall Mode Control in DIII-D Resistive Wall Mode Control in DIII-D by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil

More information

DIII D. by M. Okabayashi. Presented at 20th IAEA Fusion Energy Conference Vilamoura, Portugal November 1st - 6th, 2004.

DIII D. by M. Okabayashi. Presented at 20th IAEA Fusion Energy Conference Vilamoura, Portugal November 1st - 6th, 2004. Control of the Resistive Wall Mode with Internal Coils in the Tokamak (EX/3-1Ra) Active Measurement of Resistive Wall Mode Stability in Rotating High Beta Plasmas (EX/3-1Rb) by M. Okabayashi Presented

More information

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations Dynamical plasma response of resistive wall modes to changing external magnetic perturbations M. Shilov, C. Cates, R. James, A. Klein, O. Katsuro-Hopkins, Y. Liu, M. E. Mauel, D. A. Maurer, G. A. Navratil,

More information

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a PHYSICS OF PLASMAS VOLUME 11, NUMBER 5 MAY 2004 Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a M. Shilov, b) C. Cates, R. James, A. Klein, O. Katsuro-Hopkins,

More information

Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas

Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas 1 EX/5-3Ra Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas H. Reimerdes 1), A.M. Garofalo 2), E.J. Strait 2), R.J. Buttery 3), M.S. Chu 2), Y. In 4),

More information

The Effects of Noise and Time Delay on RWM Feedback System Performance

The Effects of Noise and Time Delay on RWM Feedback System Performance The Effects of Noise and Time Delay on RWM Feedback System Performance O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York,

More information

STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK

STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK GA A24014 STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK by M. Okabayashi, J. Bialek, M.S. Chance, M.S. Chu, E.D. Fredrickson, A.M. Garofalo, R. Hatcher, T.H.

More information

Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance

Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance M.Okabayashi, M. Chance, M. Chu* and R. Hatcher A. Garofalo**, R. La Haye*, H. Remeirdes**, T. Scoville*, and T.

More information

Effects of Noise in Time Dependent RWM Feedback Simulations

Effects of Noise in Time Dependent RWM Feedback Simulations Effects of Noise in Time Dependent RWM Feedback Simulations O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York, NY USA) Building

More information

GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS

GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS by H. REIMERDES, A.M. GAROFALO, E.J. STRAIT, R.J. BUTTERY, M.S. CHU, Y. In, G.L. JACKSON, R.J.

More information

RWM Control in FIRE and ITER

RWM Control in FIRE and ITER RWM Control in FIRE and ITER Gerald A. Navratil with Jim Bialek, Allen Boozer & Oksana Katsuro-Hopkins MHD Mode Control Workshop University of Texas-Austin 3-5 November, 2003 OUTLINE REVIEW OF VALEN MODEL

More information

Effect of an error field on the stability of the resistive wall mode

Effect of an error field on the stability of the resistive wall mode PHYSICS OF PLASMAS 14, 022505 2007 Effect of an error field on the stability of the resistive wall mode Richard Fitzpatrick Institute for Fusion Studies, Department of Physics, University of Texas at Austin,

More information

Requirements for Active Resistive Wall Mode (RWM) Feedback Control

Requirements for Active Resistive Wall Mode (RWM) Feedback Control Requirements for Active Resistive Wall Mode (RWM) Feedback Control Yongkyoon In 1 In collaboration with M.S. Chu 2, G.L. Jackson 2, J.S. Kim 1, R.J. La Haye 2, Y.Q. Liu 3, L. Marrelli 4, M. Okabayashi

More information

GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS

GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS by M. OKABAYASHI, I.N. BOGATU, T. BOLZONELLA, M.S. CHANCE, M.S. CHU, A.M. GAROFALO, R. HATCHER, Y. IN, G.L. JACKSON,

More information

CSA$-9 k067s-~ STUDY OF THE RESISTIVE WALL MODE IN DIII-D GAMA22921 JULY 1998

CSA$-9 k067s-~ STUDY OF THE RESISTIVE WALL MODE IN DIII-D GAMA22921 JULY 1998 STUDY OF THE RESISTIVE WALL MODE IN DIIID GAMA22921 CSA$9 k067s~ by A.M. GAROFALO, J. BIALEK, M.S. CHU, E.D. FREDRICKSON, R.J. GROEBNER, R.J. La HAYE, L.L. LAO, G.A. NAVRATIL, B.W. RICE, S.A. SABBAGH,

More information

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI by J.M. HANSON, F. TURCO M.J. LANCTOT, J. BERKERY, I.T. CHAPMAN, R.J. LA HAYE, G.A. NAVRATIL, M. OKABAYASHI, H. REIMERDES, S.A. SABBAGH,

More information

Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas

Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas J. P. Levesque April 12, 2011 1 Outline Basic Resistive Wall Mode (RWM) model RWM stability, neglecting kinetic effects Sufficient for

More information

Resistive wall mode stabilization by slow plasma rotation in DIII-D tokamak discharges with balanced neutral beam injection a

Resistive wall mode stabilization by slow plasma rotation in DIII-D tokamak discharges with balanced neutral beam injection a PHYSICS OF PLASMAS 14, 056101 2007 Resistive wall mode stabilization by slow plasma rotation in DIII-D tokamak discharges with balanced neutral beam injection a E. J. Strait, b A. M. Garofalo, c G. L.

More information

A simple model of the resistive wall mode in tokamaks

A simple model of the resistive wall mode in tokamaks A simple model of the resistive wall mode in tokamaks Richard Fitzpatrick Institute for Fusion Studies, Department of Physics, University of Texas at Austin, Austin TX 78712 (February 18, 2003) A simple

More information

Advances in Global MHD Mode Stabilization Research on NSTX

Advances in Global MHD Mode Stabilization Research on NSTX 1 EX/5-1 Advances in Global MHD Mode Stabilization Research on NSTX S.A. Sabbagh 1), J.W. Berkery 1), R.E. Bell 2), J.M. Bialek 1), S.P. Gerhardt 2), J.E. Menard 2), R. Betti 3), D.A. Gates 2), B. Hu 3),

More information

Plasma Stability in Tokamaks and Stellarators

Plasma Stability in Tokamaks and Stellarators Plasma Stability in Tokamaks and Stellarators Gerald A. Navratil GCEP Fusion Energy Workshop Princeton, NJ 1- May 006 ACKNOWLEDGEMENTS Borrowed VGs from many colleagues: J. Bialek, A. Garofalo,R. Goldston,

More information

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges by J.R. Ferron with T.C. Luce, P.A. Politzer, R. Jayakumar, * and M.R. Wade *Lawrence Livermore

More information

NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997

NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997 NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU General Atomics Nimrod Project Review Meeting July 21 22, 1997 Work supported by the U.S. Department of Energy under Grant DE-FG03-95ER54309 and Contract

More information

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.

More information

Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas *

Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas * 1 EX/P8-07 Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas * J.W. Berkery 1, S.A. Sabbagh 1, A. Balbaky 1, R.E. Bell 2, R. Betti 3, J.M. Bialek 1, A. Diallo 2, D.A.

More information

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University

More information

Modeling of resistive wall mode and its control in experiments and ITER a

Modeling of resistive wall mode and its control in experiments and ITER a Modeling of resistive wall mode and its control in experiments and ITER a Yueqiang Liu b Department of Applied Mechanics, EURATOM/VR Fusion Association, Chalmers University of Technology, Göteborg, Sweden

More information

Modeling of active control of external magnetohydrodynamic instabilities*

Modeling of active control of external magnetohydrodynamic instabilities* PHYSICS OF PLASMAS VOLUME 8, NUMBER 5 MAY 2001 Modeling of active control of external magnetohydrodynamic instabilities* James Bialek, Allen H. Boozer, M. E. Mauel, and G. A. Navratil Department of Applied

More information

Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research

Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research 1 TH/P9-10 Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research S. Günter, M. Garcia-Munoz, K. Lackner, Ph. Lauber, P. Merkel, M. Sempf, E. Strumberger, D. Tekle and

More information

Princeton Plasma Physics Laboratory. Multi-mode analysis of RWM feedback with the NMA Code

Princeton Plasma Physics Laboratory. Multi-mode analysis of RWM feedback with the NMA Code Princeton Plasma Physics Laboratory Multi-mode analysis of RWM feedback with the NMA Code M. S. Chance, M.Okabayashi, M. S. Chu 12 th Workshop on MHD Stability Control: Improved MHD Control Configurations

More information

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D by A. WINGEN, N.M. FERRARO, M.W. SHAFER, E.A. UNTERBERG, T.E. EVANS, D.L. HILLIS, and P.B. SNYDER JULY 2014 DISCLAIMER This report was

More information

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK GA A24738 STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK by T.C. LUCE, C.C. PETTY, D.A. HUMPHREYS, R.J. LA HAYE, and R. PRATER JULY 24 DISCLAIMER This

More information

Performance limits. Ben Dudson. 24 th February Department of Physics, University of York, Heslington, York YO10 5DD, UK

Performance limits. Ben Dudson. 24 th February Department of Physics, University of York, Heslington, York YO10 5DD, UK Performance limits Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 24 th February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 24) Previously... In the last few

More information

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Aaron J. Redd for the Pegasus Team 2008 Innovative Confinement Concepts Workshop Reno, Nevada June 24-27,

More information

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta 1 THS/P2-05 KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta Y.S. Park 1), S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), Y.M. Jeon 2), S.H. Hahn 2), N. Eidietis

More information

Resistive Wall Mode Stabilization and Plasma Rotation Damping Considerations for Maintaining High Beta Plasma Discharges in NSTX

Resistive Wall Mode Stabilization and Plasma Rotation Damping Considerations for Maintaining High Beta Plasma Discharges in NSTX 1 EXS/5-5 Resistive Wall Mode Stabilization and Plasma Rotation Damping Considerations for Maintaining High Beta Plasma Discharges in NSTX S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), R.E. Bell ),

More information

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas by T.M. Wilks 1 with A. Garofalo 2, K.H. Burrell 2, Xi. Chen 2, P.H. Diamond 3, Z.B. Guo 3, X. Xu

More information

MAGNETIC FIELD ERRORS: RECONCILING MEASUREMENT, MODELING AND EMPIRICAL CORRECTIONS ON DIII D

MAGNETIC FIELD ERRORS: RECONCILING MEASUREMENT, MODELING AND EMPIRICAL CORRECTIONS ON DIII D MAGNETIC FIELD ERRORS: RECONCILING MEASUREMENT, MODELING AND EMPIRICAL CORRECTIONS ON DIII D by M.J. Schaffer, T.E. Evans, J.L. Luxon, G.L. Jackson, J.A. Leuer, J.T. Scoville Paper QP1.76 Presented at

More information

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER by A.M. GAROFALO, K.H. BURRELL, M.J. LANCTOT, H. REIMERDES, W.M. SOLOMON and L. SCHMITZ OCTOBER 2010 DISCLAIMER This report was

More information

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles 1 EXD/P3-01 Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles J-W. Ahn 1, J.M. Canik 1, R. Maingi 1, T.K. Gray 1, J.D. Lore 1, A.G. McLean 1, J.-K. Park 2, A.L.

More information

RWM Control Code Maturity

RWM Control Code Maturity RWM Control Code Maturity Yueqiang Liu EURATOM/CCFE Fusion Association Culham Science Centre Abingdon, Oxon OX14 3DB, UK Work partly funded by UK EPSRC and EURATOM. The views and opinions expressed do

More information

Interaction of scrape-off layer currents with magnetohydrodynamical instabilities in tokamak plasmas

Interaction of scrape-off layer currents with magnetohydrodynamical instabilities in tokamak plasmas Interaction of scrape-off layer currents with magnetohydrodynamical instabilities in tokamak plasmas Richard Fitzpatrick Institute for Fusion Studies Department of Physics University of Texas at Austin

More information

Flow and dynamo measurements in the HIST double pulsing CHI experiment

Flow and dynamo measurements in the HIST double pulsing CHI experiment Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M.

More information

AC loop voltages and MHD stability in RFP plasmas

AC loop voltages and MHD stability in RFP plasmas AC loop voltages and MHD stability in RFP plasmas K. J. McCollam, D. J. Holly, V. V. Mirnov, J. S. Sar, D. R. Stone UW-Madison 54rd Annual Meeting of the APS-DPP October 29th - November 2nd, 2012 Providence,

More information

Current Drive Experiments in the HIT-II Spherical Tokamak

Current Drive Experiments in the HIT-II Spherical Tokamak Current Drive Experiments in the HIT-II Spherical Tokamak T. R. Jarboe, P. Gu, V. A. Izzo, P. E. Jewell, K. J. McCollam, B. A. Nelson, R. Raman, A. J. Redd, P. E. Sieck, and R. J. Smith, Aerospace & Energetics

More information

MHD Linear Stability Analysis Using a Full Wave Code

MHD Linear Stability Analysis Using a Full Wave Code US-Japan JIFT Workshop on Progress of Extended MHD Models NIFS, Toki,Japan 2007/03/27 MHD Linear Stability Analysis Using a Full Wave Code T. Akutsu and A. Fukuyama Department of Nuclear Engineering, Kyoto

More information

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control P. A. Politzer, 1 A. W. Hyatt, 1 T. C. Luce, 1 F. W. Perkins, 4 R. Prater, 1 A. D. Turnbull, 1 D. P. Brennan, 5 J.

More information

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation - 15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect

More information

Supported by. Role of plasma edge in global stability and control*

Supported by. Role of plasma edge in global stability and control* NSTX Supported by College W&M Colorado Sch Mines Columbia U CompX General Atomics INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U

More information

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Observation of Neo-Classical Ion Pinch in the Electric Tokamak* 1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,

More information

Evaluation of CT injection to RFP for performance improvement and reconnection studies

Evaluation of CT injection to RFP for performance improvement and reconnection studies Evaluation of CT injection to RFP for performance improvement and reconnection studies S. Masamune A. Sanpei, T. Nagano, S. Nakanobo, R. Tsuboi, S. Kunita, M. Emori, H. Makizawa, H. Himura, N. Mizuguchi

More information

Plasma Response Control Using Advanced Feedback Techniques

Plasma Response Control Using Advanced Feedback Techniques Plasma Response Control Using Advanced Feedback Techniques by M. Clement 1 with J. M. Hanson 1, J. Bialek 1 and G. A. Navratil 1 1 Columbia University Presented at 59 th Annual APS Meeting Division of

More information

Disruption dynamics in NSTX. long-pulse discharges. Presented by J.E. Menard, PPPL. for the NSTX Research Team

Disruption dynamics in NSTX. long-pulse discharges. Presented by J.E. Menard, PPPL. for the NSTX Research Team Disruption dynamics in NSTX long-pulse discharges Presented by J.E. Menard, PPPL for the NSTX Research Team Workshop on Active Control of MHD Stability: Extension of Performance Monday, November 18, 2002

More information

Non-Solenoidal Plasma Startup in

Non-Solenoidal Plasma Startup in Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique

More information

Oscillating-Field Current-Drive Experiment on MST

Oscillating-Field Current-Drive Experiment on MST Oscillating-Field Current-Drive Experiment on MST K. J. McCollam, J. K. Anderson, D. J. Den Hartog, F. Ebrahimi, J. A. Reusch, J. S. Sarff, H. D. Stephens, D. R. Stone University of Wisconsin-Madison D.

More information

ELMs and Constraints on the H-Mode Pedestal:

ELMs and Constraints on the H-Mode Pedestal: ELMs and Constraints on the H-Mode Pedestal: A Model Based on Peeling-Ballooning Modes P.B. Snyder, 1 H.R. Wilson, 2 J.R. Ferron, 1 L.L. Lao, 1 A.W. Leonard, 1 D. Mossessian, 3 M. Murakami, 4 T.H. Osborne,

More information

Comparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR

Comparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR 1 Comparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR W. Choe 1,2*, K. Kim 1,2, J.-W. Ahn 3, H.H. Lee 4, C.S. Kang 4, J.-K. Park 5, Y. In 4, J.G. Kwak 4,

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK

More information

A New Resistive Response to 3-D Fields in Low Rotation H-modes

A New Resistive Response to 3-D Fields in Low Rotation H-modes in Low Rotation H-modes by Richard Buttery 1 with Rob La Haye 1, Yueqiang Liu 2, Bob Pinsker 1, Jong-kyu Park 3, Holger Reimerdes 4, Ted Strait 1, and the DIII-D research team. 1 General Atomics, USA 2

More information

Progress Toward High Performance Steady-State Operation in DIII D

Progress Toward High Performance Steady-State Operation in DIII D Progress Toward High Performance Steady-State Operation in DIII D by C.M. Greenfield 1 for M. Murakami, 2 A.M. Garofalo, 3 J.R. Ferron, 1 T.C. Luce, 1 M.R. Wade, 1 E.J. Doyle, 4 T.A. Casper, 5 R.J. Jayakumar,

More information

Magnetic Control of Perturbed Plasma Equilibria

Magnetic Control of Perturbed Plasma Equilibria Magnetic Control of Perturbed Plasma Equilibria Nikolaus Rath February 17th, 2012 N. Rath (Columbia University) Magnetic Control of Perturbed Plasma Equilibria February 17th, 2012 1 / 19 The HBT-EP Tokamak

More information

Analytical Study of RWM Feedback Stabilisation with Application to ITER

Analytical Study of RWM Feedback Stabilisation with Application to ITER CT/P- Analytical Study of RWM Feedback Stabilisation with Application to ITER Y Gribov ), VD Pustovitov ) ) ITER International Team, ITER Naka Joint Work Site, Japan ) Nuclear Fusion Institute, Russian

More information

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Non-solenoidal startup using point-source DC helicity injectors

More information

1 EX/P7-12. Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments

1 EX/P7-12. Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments 1 EX/P7-12 Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments Y. Ono 1), R. Imazawa 1), H. Imanaka 1), T. Hayamizu 1), M. Inomoto 1), M. Sato 1), E. Kawamori 1),

More information

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Z. Yan 1, G.R. McKee 1, J.A. Boedo 2, D.L. Rudakov 2, P.H. Diamond 2, G. Tynan 2, R.J. Fonck 1, R.J. Groebner 3, T.H. Osborne 3, and

More information

(Motivation) Reactor tokamaks have to run without disruptions

(Motivation) Reactor tokamaks have to run without disruptions Abstract A database has been developed to study the evolution, the nonlinear effects on equilibria, and the disruptivity of locked and quasi-stationary modes with poloidal and toroidal mode numbers m=2

More information

Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain

Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain arxiv:146.5245v1 [physics.plasm-ph] 2 Jun 214 D. P. Brennan and J. M. Finn June 23, 214 Department of Astrophysical

More information

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. Lin-Liu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,

More information

Advanced Tokamak Research in JT-60U and JT-60SA

Advanced Tokamak Research in JT-60U and JT-60SA I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development

More information

IMPACT OF EDGE CURRENT DENSITY AND PRESSURE GRADIENT ON THE STABILITY OF DIII-D HIGH PERFORMANCE DISCHARGES

IMPACT OF EDGE CURRENT DENSITY AND PRESSURE GRADIENT ON THE STABILITY OF DIII-D HIGH PERFORMANCE DISCHARGES IMPACT OF EDGE CURRENT DENSITY AND PRESSURE GRADIENT ON THE STABILITY OF DIII-D HIGH PERFORMANCE DISCHARGES by L.L. LAO, J.R. FERRON, E.J. STRAIT, V.S. CHAN, M.S. CHU, E.A. LAZARUS, TIC. LUCE, R.L. MILLER,

More information

Feedback stabilization of the resistive shell mode in a tokamak fusion reactor

Feedback stabilization of the resistive shell mode in a tokamak fusion reactor Feedback stabilization of the resistive shell mode in a tokamak fusion reactor Institute for Fusion Studies, Department of Physics, The University of Texas at Austin, Austin, Texas 78712 Received 16 September

More information

Physics and Operations Plan for LDX

Physics and Operations Plan for LDX Physics and Operations Plan for LDX Columbia University A. Hansen D.T. Garnier, M.E. Mauel, T. Sunn Pedersen, E. Ortiz Columbia University J. Kesner, C.M. Jones, I. Karim, P. Michael, J. Minervini, A.

More information

GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE STABILITY IN DIII D

GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE STABILITY IN DIII D GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE by L.L. LAO, V.S. CHAN, L. CHEN, E.J. DOYLE, J.R. FERRON, R.J. GROEBNER, G.L. JACKSON, R.J. LA HAYE, E.A. LAZARUS, G.R. McKEE, R.L. MILLER, M. MURAKAMI,

More information

EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY*

EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY* EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY* by K.H. BURRELL Presented at the Transport Task Force Meeting Annapolis, Maryland April 3 6, 22 *Work supported by U.S. Department of Energy

More information

The Effect of Energetic Particles on Resistive Wall Mode Stability in MAST

The Effect of Energetic Particles on Resistive Wall Mode Stability in MAST The Effect of Energetic Particles on Resistive Wall Mode Stability in MAST IT Chapman 1, MP Gryaznevich 1, DF Howell 1, YQ Liu 1 and the MAST Team 1 EURATOM/CCFE Fusion Association, Culham Science Centre,

More information

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak 1 EXS/P2-19 Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak T. Yamada 1), R. Imazawa 2), S. Kamio 1), R. Hihara 1), K. Abe 1), M. Sakumura 1), Q. H. Cao 1), H. Sakakita

More information

Fast Ion Confinement in the MST Reversed Field Pinch

Fast Ion Confinement in the MST Reversed Field Pinch Fast Ion Connement in the MST Reversed Field Pinch Gennady Fiksel B. Hudson, D.J. Den Hartog, R.M. Magee, R. O'Connell, S.C. Prager MST Team - University of Wisconsin - Madison Center for Magnetic Self-Organization

More information

Magnetic Diagnostics Basics

Magnetic Diagnostics Basics Abstract We report measurement of the equilibrium plasma current profiles in the Levitated Dipole Experiment (LDX) that exhibit a peak beta in excess of 10 percent. The beta of an LDX plasma is calculated

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual

More information

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 J Fusion Energ (2010) 29:553 557 DOI 10.1007/s10894-010-9327-6 ORIGINAL RESEARCH Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 H. Saitoh Z. Yoshida J. Morikawa Y. Yano T. Mizushima

More information

On the physics of shear flows in 3D geometry

On the physics of shear flows in 3D geometry On the physics of shear flows in 3D geometry C. Hidalgo and M.A. Pedrosa Laboratorio Nacional de Fusión, EURATOM-CIEMAT, Madrid, Spain Recent experiments have shown the importance of multi-scale (long-range)

More information

Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator

Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator EX/P- Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator Á. Cappa, F. Castejón, T. Estrada, J.M. Fontdecaba, M. Liniers and E. Ascasíbar Laboratorio Nacional de Fusión CIEMAT,

More information

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations 1 EXC/P5-02 ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science

More information

MHD instability driven by supra-thermal electrons in TJ-II stellarator

MHD instability driven by supra-thermal electrons in TJ-II stellarator MHD instability driven by supra-thermal electrons in TJ-II stellarator K. Nagaoka 1, S. Yamamoto 2, S. Ohshima 2, E. Ascasíbar 3, R. Jiménez-Gómez 3, C. Hidalgo 3, M.A. Pedrosa 3, M. Ochando 3, A.V. Melnikov

More information

THE DIII D PROGRAM THREE-YEAR PLAN

THE DIII D PROGRAM THREE-YEAR PLAN THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned

More information

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Concept Overview Implementation on PEGASUS Results Current

More information

Current-driven instabilities

Current-driven instabilities Current-driven instabilities Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 21 st February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously In the last

More information

DIII D Research in Support of ITER

DIII D Research in Support of ITER Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design

More information

1999 RESEARCH SUMMARY

1999 RESEARCH SUMMARY 1999 RESEARCH SUMMARY by S.L. Allen Presented to DIII D Program Advisory Committee Meeting January 2 21, 2 DIII D NATIONAL FUSION FACILITY SAN DIEGO 3 /SLA/wj Overview of Physics Results from the 1999

More information

Stabilization of sawteeth in tokamaks with toroidal flows

Stabilization of sawteeth in tokamaks with toroidal flows PHYSICS OF PLASMAS VOLUME 9, NUMBER 7 JULY 2002 Stabilization of sawteeth in tokamaks with toroidal flows Robert G. Kleva and Parvez N. Guzdar Institute for Plasma Research, University of Maryland, College

More information

Behavior of Compact Toroid Injected into the External Magnetic Field

Behavior of Compact Toroid Injected into the External Magnetic Field Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa

More information

Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter

Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Matthias Hölzl Nonlinear ELM Simulations DPG Spring Meeting, Jena, 02/2013

More information

Two Fluid Dynamo and Edge-Resonant m=0 Tearing Instability in Reversed Field Pinch

Two Fluid Dynamo and Edge-Resonant m=0 Tearing Instability in Reversed Field Pinch 1 Two Fluid Dynamo and Edge-Resonant m= Tearing Instability in Reversed Field Pinch V.V. Mirnov 1), C.C.Hegna 1), S.C. Prager 1), C.R.Sovinec 1), and H.Tian 1) 1) The University of Wisconsin-Madison, Madison,

More information

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas 1 PD/1-1 First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas R. Nazikian 1, W. Suttrop 2, A. Kirk 3, M. Cavedon 2, T.E. Evans

More information

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL th IAEA Fusion Energy Conference Vilamoura, Portugal, to 6 November IAEA-CN-6/EX/P-7 STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL P.A. POLITZER, A.W. HYATT, T.C.

More information

Effect of ideal kink instabilities on particle redistribution

Effect of ideal kink instabilities on particle redistribution Effect of ideal kink instabilities on particle redistribution H. E. Ferrari1,2,R. Farengo1, P. L. Garcia-Martinez2, M.-C. Firpo3, A. F. Lifschitz4 1 Comisión Nacional de Energía Atómica, Centro Atomico

More information

of HIGH betan*h SIMULATIONS TOKAMAK ADVANCED IN DIII-D WITH DISCHARGES 3D NONLINEAR CODE NFTC. THE N.N.Popova A.M.Popov, State University Moscow La Ha

of HIGH betan*h SIMULATIONS TOKAMAK ADVANCED IN DIII-D WITH DISCHARGES 3D NONLINEAR CODE NFTC. THE N.N.Popova A.M.Popov, State University Moscow La Ha of HIGH betan*h SIMULATIONS TOKAMAK ADVANCED IN DIII-D WITH DISCHARGES 3D NONLINEAR CODE NFTC. THE N.N.Popova A.M.Popov, State University Moscow La Haye, A.D.Turnbull V.S.Chan,R.J. Atomics General M.Murakami

More information

Spatio-temporal investigations on the triggering of pellet induced ELMs

Spatio-temporal investigations on the triggering of pellet induced ELMs Spatio-temporal investigations on the triggering of pellet induced ELMs G. Kocsis, S. Kálvin, P.T. Lang*, M. Maraschek*, J. Neuhauser* W. Schneider*, T. Szepesi and ASDEX Upgrade Team KFKI-RMKI, EURATOM

More information

MHD-Induced Alpha Particle Loss in TFTR. S.J. Zweben, D.S. Darrow, E.D. Fredrickson, G. Taylor, S. von Goeler, R.B. White

MHD-Induced Alpha Particle Loss in TFTR. S.J. Zweben, D.S. Darrow, E.D. Fredrickson, G. Taylor, S. von Goeler, R.B. White MHD-Induced Alpha Particle Loss in TFTR S.J. Zweben, D.S. Darrow, E.D. Fredrickson, G. Taylor, S. von Goeler, R.B. White Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, NJ 8543 Abstract MHD-induced

More information