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

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

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

Transcription

1 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 at th IAEA Fusion Energy Conference Vilamoura, Portugal November 1st - 6th, /MRW//rs

2 EX/3-1Ra CONTROL OF THE RESISTIVE WALL MODE WITH INTERNAL COILS IN THE TOKAMAK M. Okabayashi, J. Bialek, A. Bondeson, M.S. Chance, M.S. Chu, D.H. Edgell, A.M. Garofalo, R. Hatcher, 1Y. In, 4 G.L. Jackson, 3R.J. Jayakumar, 5 T.H. Jensen, + O. Katsuro-Hopkins, R.J. La Haye, Y.Q. Liu, G.A. Navratil, H. Reimerdes, J.T. Scoville, E.J. Strait, 3 1 H. Takahashi, M. Takechi, 7, A.D. Turnbull, 3 I.N. Bogatu, 4 P. Gohil, 3 J.S. Kim, 4 M.A. Makowski, 5 J. Manickam, 1 and J. Menard Princeton Plasma Physics Laboratory, Princeton, New Jersey, ,USA Columbia University, New York, New York, USA. 3 General Atomics, P.O. Box 8568, San Diego, California , USA. 4 Far-Tech, Inc., San Diego, California 911, USA. 5 Lawrence Livermore National Laboratory, Livermore, California, USA. 6 Chalmers University of Technology, Goteborg, Sweden. 7 Japan Atomic Energy Research Institute, Ibaraki, Japan +deceased th IAEA Fusion Energy Conference, Vilamoura, Portugal 4

3 EX/3-1Rb ACTIVE MEASUREMENT OF RESISTIVE WALL MODE STABILITY IN ROTATING HIGH BETA PLASMAS H. Reimerdes,1 J. Bialek,1 M.S. Chance, M.S. Chu,3 A.M. Garofalo,1 P. Gohil,3 G.L. Jackson,3 R.J. Jayakumar,4 T.H. Jensen, + R.J. La Haye,3 Y.Q. Liu,5 J.E. Menard, G.A. Navratil,1 M. Okabayashi, J.T. Scoville,3 E.J. Strait,3 and H. Takahashi, 1 Columbia University, New York, New York, USA Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA 3 General Atomics, San Diego, California, USA 4 Lawrence Livermore National Laboratory, Livermore, California, USA 5 Chalmers University of Technology, Göteborg, Sweden + deceased th IAEA Fusion Energy Conference, Vilamoura, Portugal 4

4 EXTERNAL KINK CONTROL WITH RESISTIVE WALL l Steady state advanced tokamak scenarios need wall stabilization of external kink modes for operation at high beta with a high fraction of bootstrap current l Finite-conductivity wall Does not completely stabilize ideal kink mode, Converts it to a slowly-growing Resistive Wall Mode (RWM) l Two approaches to RWM stabilization Passive: fast plasma rotation (EX/3-1Rb) Active: magnetic feedback control (EX/3-1a) l New Internal coils installed just after the last IAEA conference: Very productive for RWM physics studies and active control of RWMs Active MHD spectroscopy with applied rotating field: RWM stability physics Plasma rotation sustained by feedback-controlled error field correction: Long duration high b plasmas Direct feedback control : RWM stability at higher beta below critical rotation

5 NEW INTERNAL CONTROL COILS ARE AN EFFECTIVE TOOL FOR PURSUING STABILIZATION OF THE RWM Inside vacuum vessel: Faster time response for feedback control Closer to plasma, flexible magnetic field pattern: more efficient coupling 1 "picture-frame" coils Single-turn, water-cooled 7 ka max. rated current Protected by graphite tiles 1 gauss/ka on plasma surface B P Sensors Internal Coils

6 NEW INTERNAL CONTROL COILS ARE AN EFFECTIVE TOOL FOR PURSUING STABILIZATION OF THE RWM Inside vacuum vessel: Faster time response for feedback control Closer to plasma, flexible magnetic field pattern: more efficient coupling 1 "picture-frame" coils Single-turn, water-cooled 7 ka max. rated current Protected by graphite tiles 1 gauss/ka on plasma surface Vacuum Vessel (Cutaway View) External Coils (C-coils)

7 FEEDBACK WITH I-COILS INCREASES STABLE PLASMA PRESSURE TO NEAR IDEAL-WALL LIMIT l VALEN code prediction Normalized Growth Rate gt w No Feedback Ideal kink l VALEN code: - DCON MHD stability - 3D geometry of vacuum vessel and coil geometry Resistive Wall Mode: Open loop growth rate l t w is the vacuum vessel flux diffusion time (5 ms is used in VALEN code). No-Wall Limit C b =.4 b C b.6.8 b - b no.wall ideal.wall - b no.wall 1. Ideal-Wall Limit

8 FEEDBACK WITH I-COILS INCREASES STABLE PLASMA PRESSURE TO NEAR IDEAL-WALL LIMIT l C-coil stabilizes Slowly growing RWMs Normalized Growth Rate gt w No-Wall Limit No Feedback External C-coils Accessible with External C-coils C b =.4 b C b.6 Ideal kink.8 b - b no.wall ideal.wall - b no.wall 1. Ideal-Wall Limit l VALEN code: - DCON MHD stability - 3D geometry of vacuum vessel and coil geometry l t w is the vacuum vessel flux diffusion time constant (5 ms is used in VALEN code)

9 FEEDBACK WITH I-COILS INCREASES STABLE PLASMA PRESSURE TO NEAR IDEAL-WALL LIMIT l I-coil stabilizes RWMs with growth rate 1 times faster than C-coils Normalized Growth Rate gt w No-Wall Limit No Feedback External C-coils Internal I-coils Accessible with External C-coils C b =.4 b C b.6 Accessible with Internal I-coils Ideal kink.8 b - b no.wall ideal.wall - b no.wall 1. Ideal-Wall Limit l VALEN code: - DCON MHD stability - 3D geometry of vacuum vessel and coil geometry l t w is the vacuum vessel flux diffusion time (5 ms is used in VALEN code)

10 γτ w 3 OBSERVED OPEN LOOP GROWTH RATES AGREE WITH VALEN PREDICTION VALEN prediction No Feedback 1 C 1. No-wall β Ideal-wall limit limit

11 TWO DISTINCT STABILIZATION APPROACHES HAVE BEEN PROPOSED Plasma Rotation Required: A few % of Alfven velocity 8. Ω = Magnetic Feedback Required: Practical power level System stability limits gain 8. Ω = γτ w -. No-Wall Limit STABLE β Exp/3-1Rb Increase Rotation Ideal-Wall Limit γτ w -. No-Wall Limit Gain = β Exp/3-1Ra Higher Gain STABLE Ideal-Wall Limit

12 WALL STABILIZATION WITH ROTATION ALLOWS HIGH BETA OPERATION l Stable at b N ª 6 l i and b T reaching to 6% l Beta exceeds estimated no-wall limit for >1s ( > t w ) b N 4li ~ Estimated No-Wall Limit 1154 l Broad current profiles can greatly benefit from wall stabilization t= ms q J b (A/cm ) T (%) q Normalized r ~.6 (q=) 1 Rotation W rot / W A (%) r Time (ms)

13 HOW MUCH PLASMA ROTATION IS REQUIRED TO STABILIZE THE n=1 RWM? 3 β N ~Estimated no-wall limit 1 15 Ω rot/(π) at ρ=.6 (khz) Ω crit /(π) BESL n=1 amplitude (Gauss) Time (ms) Insufficient error field correction causes slow-down Onset of RWM marks critical rotation Ω crit Measured rotation threshold Ω crit /Ω A (%) (q = ) no wall limit C β.5 1. ideal wall limit

14 HOW MUCH PLASMA ROTATION IS REQUIRED TO STABILIZE THE n=1 RWM? 3 β N ~Estimated no-wall limit 1 15 Ω rot/(π) at ρ=.6 (khz) Ω crit /(π) BESL n=1 amplitude (Gauss) Time (ms) Insufficient error field correction causes slow-down Onset of RWM marks critical rotation Ω crit Comparison with MARS calculation with experimental rotation profile -.5 Ω crit /Ω A (%) (q = ) Soundwave damping overestimates the critical rotation kinetic sound wave (κ =.5).5 1 C β no wall limit ideal wall limit Kinetic damping underestimates the critical rotation MARS includes rotation and viscous dissipation

15 β N Upper I coil (φ=3deg) (ka) (1 Hz) Midplane Br (φ=139deg) (Gauss) (1 Hz) Magnitude of n=1 plasma response (Gauss/kA) Tor. phase of n=1 plasma response (Deg.) MHD SPECTROSCOPY PROBES THE RWM STABILITY WHILE THE PLASMA REMAINS STABLE no-wall limit - Hz C β ~.5 Estimated no-wall limit Hz - Hz +4 Hz Direction +1 Hz of plasma rotation +4 Hz 1 Time (ms) Plasma Response Amplitude and phase Amplitude Experiment / fit / t=15ms / t=18ms C β ~.4 Phase shift (Deg.) C β ~.5-4 Frequency of applied field (Hz)

16 SPECTRUM REVEALS GROWTH RATE AND MODE ROTATION FREQUENCY OF THE STABLE RWM. Amplitude C β ~.5 Spectrum Analysis with a Single Mode Model γ =γ RWM + i ω RWM Growth rate γ RWM τ W experiment C β ~.4 phase shift (Deg.) Amplification Factor = M (1+γ τ w ) (iω ext τ w - γ τ w ) Coupling between external field and RWM Mode rotation frequency ω RWM τ W -4 Experiment / fit / t=15ms / t=18ms - 4 Frequency of applied field (Hz) C β

17 SPECTRUM REVEALS GROWTH RATE AND MODE ROTATION FREQUENCY OF THE STABLE RWM. Amplitude C β ~.5 Spectrum Analysis with a Single Mode Model γ =γ RWM + i ω RWM Growth rate γ RWM τ W experiment Experiment / fit / t=15ms / t=18ms - 4 Frequency of applied field (Hz) C β ~.4 phase shift (Deg.) Amplification Factor = M (1+γ τ w ) (iω ext τ w - γ τ w ) MARS Comparison Growth rate Coupling between external field and RWM - sound wave / kinetic overestimates stabilizing effect Mode rotation frequency - kinetic : agreement - sound wave damping underestimate coupling kinetic sound wave (κ =.5) Mode rotation frequency ω RWM τ W C β

18 TWO DISTINCT STABILIZATION APPROACHES HAVE BEEN PROPOSED Plasma Rotation Required: A few % of Alfven velocity 8. Magnetic Feedback Required: Practical power level System stability limits gain 8. Ω = γτ w -. No-Wall Limit STABLE β Increase Rotation Ideal-Wall Limit γτ w -. No-Wall Limit Gain = β Higher Gain STABLE Ideal-Wall Limit Ω rot > Ω crit Ω rot < Ω crit Rational surface damping mechanism > Ω at q= as a measure of rotations

19 DIRECT MAGNETIC FEEDBACK SUSTAINS BETA ABOVE NO-WALL LIMIT EVEN WHEN Ω rot < Ω crit βn.4l i Estimated no-wall limit 3. Ωrot (%) ΩA Feedback (at q=) on 1% Feedback Current 5. (ka) -5. δbp n=1 4 Amplitude Stable (gauss) 1 13 Time (ms) Feedback off Growth time 4ms

20 FEEDBACK SUSTAINS A DISCHARGE WITH NEAR-ZERO ROTATION AT ALL n=1 RATIONAL SURFACES Comparison case without feedback is unstable even with lower beta and faster rotation 3 Rotation Ideal-Wall Frequency (khz) β /l Feedback Limit N i 3 1 No-Feedback No-Wall Limit (approx.) ms ms δb p (Gauss) 1 frot (khz) at ρ = Time (ms) Feedback Stabilized with Low Rotation q(ρ) ρ 1.

21 FEEDBACK WITH I-COILS HAS ACHIEVED HIGH b n AT ROTATION BELOW CRITICAL PREDICTED BY MARS C b = b b - b no.wall ideal.wall ideal wall limit - b no.wall C b 1. Unstable (without feedback) MARS prediction Stable (without feedback) C-COIL time no wall limit NO FEEDBACK Rotation (km/s)

22 FEEDBACK WITH I-COILS HAS ACHIEVED HIGH b n AT ROTATION BELOW CRITICAL PREDICTED BY MARS l With near zero Rotation, C b is near the maximum set by control system characteristics C b = b b - b no.wall ideal.wall ideal wall limit - b no.wall C b 1. Unstable (without feedback) MARS prediction Stable (without feedback) MARS /VALEN prediction for zero rotation, with measured feedback system time response I-COIL ªZERO ROTATION C-COIL time no wall limit NO FEEDBACK 5 1 Rotation (km/s) 15

23 FEEDBACK WITH I-COILS HAS ACHIEVED HIGH b n AT ROTATION BELOW CRITICAL PREDICTED BY MARS l With near zero Rotation, C b is near the maximum set by control system characteristics l Feedback with I-coils attained C b higher than with C-coils C b = b b - b no.wall ideal.wall ideal wall limit - b no.wall C b 1. I-COIL Unstable (without feedback) MARS prediction Stable (without feedback) MARS /VALEN prediction for zero rotation, with measured feedback system time response I-COIL ªZERO ROTATION C-COIL time no wall limit NO FEEDBACK 5 1 Rotation (km/s) 15

24 RWM FEEDBACK ASSISTS IN EXTENDING β n 4 ADVANCED TOKAMAK DISCHARGE MORE THAN 1 SECOND 4. βn Feedback current (ka) Plasma Rotation (km/s) 3 n=1 δb p Mode Amplitude (gauss) Estimated no-wall limit F.B on Feedback coil current amplitude No Feedback No Feedback With Feedback With Feedback / Time (ms) 1 The rotation is similar for both cases <j // > (A/cm ) p(ρ) (xe3 Pa) t = ms q(ρ) 5. q(ρ) ρ 1.

25 MARS ANALYSIS PREDICTS THAT STABLE FEEDBACK GAIN RANGE IS NARROW l With experimental profiles and present hardware l Stable mode becomes unstable with higher gain due to finite feedback time response Unstable mode RWM growth rate Stable mode gt w Present hardware Stable window.1. Gain (unnormalized) t w is.5 ms in MARS-F

26 MARS ANALYSIS PREDICTS THAT STABLE FEEDBACK GAIN RANGE IS NARROW l High-bandwidth audio amplifiers are being installed to increase the range of stable operation Unstable mode. 1. Present hardware Expected with audio amp. RWM growth rate -1. gt w -. audio amplifiers Stable mode Stable window Gain (unnormalized) t w is.5 ms in MARS-F

27 OVERALL SUMMARY l Active MHD Spectroscopy has been developed to investigate RWM stability (EX/3-1Rb) Detailed comparison of experiments with damping models is now possible Sound wave and kinetic damping model results are comparable to experimental values Further improvement of models is needed for a quantitative comparison l Direct magnetic feedback with I-coils has been demonstrated as an essential tool for achieving high b plasmas (EX/3-1Ra) Internal Coils are more effective and efficient than External Coils High b n close to the ideal-wall limit has been achieved with W rot < W crit Feedback has assisted in sustaining advanced tokamak discharges with b n ª 4 for over 1 second l Future work High-bandwidth Audio-amplifiers to increase the range of stable operation Counter Neutral Beam Injection for greater control of plasma rotation assessing the rotational stabilization

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

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 STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

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

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

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

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

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

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

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

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 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

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

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

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

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

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

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

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

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

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

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

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

Dynamic Resonant Error Field Correction with C-COIL and I-COIL in the DIIID device

Dynamic Resonant Error Field Correction with C-COIL and I-COIL in the DIIID device Dynamic Resnant Errr Field Crrectin with C-COIL and I-COIL in the DIIID device M. Okabayashi, M.S. Chance, R, Hatcher, J. Manickam P P P L, J. Bialek, A.M. Garfal, G.A. Navratil, H. Reimerdes, C lumbia

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

DIII D. by F. Turco 1. New York, January 23 rd, 2015

DIII D. by F. Turco 1. New York, January 23 rd, 2015 Modelling and Experimenting with ITER: the MHD Challenge by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, F. Carpanese 3, C. Paz-Soldan 2, C.C. Petty 2, T.C. Luce 2, W.M. Solomon 4,

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

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

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

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

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

Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program

Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program OV/-5 Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program K.H. Burrell for the DIII D Team General Atomics, P.O. Box 8568, San Diego, California 986-568 email: burrell@fusion.gat.com

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

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

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

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

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

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

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

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

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

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

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

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS by T.C. LUCE, G.L. JACKSON, T.W. PETRIE, R.I. PINSKER, W.M. SOLOMON, F. TURCO, N. COMMAUX, J.R. FERRON, A.M. GAROFALO,

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

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

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

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

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

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

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

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012 Impact of Torque and Rotation in High Fusion Performance Plasmas by W.M. Solomon 1 K.H. Burrell 2, R.J. Buttery 2, J.S.deGrassie 2, E.J. Doyle 3, A.M. Garofalo 2, G.L. Jackson 2, T.C. Luce 2, C.C. Petty

More information

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D GA A271 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D by C.C. PETTY, J.S. degrassie, R.W. HARVEY, Y.R. LIN-LIU, J.M. LOHR, T.C. LUCE, M.A. MAKOWSKI, Y.A. OMELCHENKO, and R. PRATER AUGUST 2001 DISCLAIMER This

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

FINITE ELEMENT CENTER

FINITE ELEMENT CENTER FINITE ELEMENT CENTER PREPRINT 25 7 Modeling of resistive wall mode and its control in experiments and ITER Yueqiang Liu, M.S. Chu, A.M. Garofalo, Y. Gribov, M. Gryaznevich, T.C. Hender, D.F. Howell, R.J.

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

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

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

Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U *

Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U * 1 EX/P4-34 Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U * J.W. Berkery 1, S.A. Sabbagh 1, Y.S. Park 1, R.E. Bell 2, S.P. Gerhardt 2, C.E. Myers 2 1 Department of

More information

Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling

Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling 1 TH/P1-18 Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling T. Bolzonella 1, P. Bettini 1, L. Figini 2, S.C. Guo 1, Y.Q. Liu 3, G. Marchiori 1, G. Matsunaga 4,

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

Plan of Off-axis Neutral Beam Injector in KSTAR

Plan of Off-axis Neutral Beam Injector in KSTAR KSTAR conference, Feb 25-27, 2015, Daejeon (DCC), Korea Plan of Off-axis Neutral Beam Injector in KSTAR Feb. 26, 2015 DCC, Daejeon, Korea Young-soon Bae a L. Terzolo a, K.S. Lee a, H.K. Kim a, H.L. Yang

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

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U EX1-4 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase, a S. Ide, b Y. Kamada, b H. Kubo, b O. Mitarai, c H. Nuga, a Y. Sakamoto, b T. Suzuki, b H. Takenaga, b and the JT-60 Team a University

More information

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions 7th APTWG Intl. Conference 5-8 June 2017 Nagoya Univ., Nagoya, Japan Andreas Bierwage, Yasushi Todo 14.1MeV 10 kev

More information

Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Frequency

Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Frequency Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Freuency by M.S. Chu In collaboration with L.L. Lao, M.J. Schaffer, T.E. Evans E.J. Strait (General Atomics)

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

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME by R. NAZIKIAN, M.E. AUSTIN, R.V. BUDNY, M.S. CHU, W.W. HEIDBRINK, M.A. MAKOWSKI, C.C. PETTY, P.A. POLITZER, W.M. SOLOMON, M.A.

More information

Control of linear modes in cylindrical resistive MHD with a resistive wall, plasma rotation, and complex gain

Control of linear modes in cylindrical resistive MHD with a resistive wall, plasma rotation, and complex gain Control of linear modes in cylindrical resistive MHD with a resistive wall, plasma rotation, and complex gain Dylan Brennan 1 and John Finn 2 contributions from Andrew Cole 3 1 Princeton University / PPPL

More information

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D by C.C. PETTY, P.A. POLITZER, R.J. JAYAKUMAR, T.C. LUCE, M.R. WADE, M.E. AUSTIN, D.P. BRENNAN, T.A. CASPER, M.S. CHU, J.C. DeBOO, E.J. DOYLE,

More information

Local organizer. National Centralized Tokamak

Local organizer. National Centralized Tokamak US/Japan Workshop on MHD Stability Control and Related Confinement of Toroidal Plasmas, 6-8 February 2006, JAEA-Naka, Japan with ITPA meeting of MHD Topical Group, 6-9 February Venue and Dates The workshop

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

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

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

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:

More information

GERALD A. NAVRATIL. Thomas Alva Edison Professor of Applied Physics Department of Applied Physics and Applied Mathematics Columbia University

GERALD A. NAVRATIL. Thomas Alva Edison Professor of Applied Physics Department of Applied Physics and Applied Mathematics Columbia University 1 GERALD A. NAVRATIL Thomas Alva Edison Professor of Applied Physics Department of Applied Physics and Applied Mathematics Columbia University 209 S. W. Mudd Building office: (212) 854-4496 Columbia University

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U 1 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase 1), S. Ide 2), Y. Kamada 2), H. Kubo 2), O. Mitarai 3), H. Nuga 1), Y. Sakamoto 2), T. Suzuki 2), H. Takenaga 2), and the JT-60 Team 1)

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

DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS

DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS GA A25808 DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS by D.A. HUMPHREYS, J.R. FERRON, A.W. HYATT, R.J. La HAYE, J.A. LEUER, B.G. PENAFLOR, M.L. WALKER, A.S. WELANDER,

More information

DIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by

DIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN Presented by C.M. GREENFIELD for J.C. DeBOO, T.C. LUCE, B.W. STALLARD, E.J. SYNAKOWSKI, L.R. BAYLOR,3 K.H. BURRELL, T.A. CASPER, E.J.

More information

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas D. Borba 1,9, R. Nazikian 2, B. Alper 3, H.L. Berk 4, A. Boboc 3, R.V. Budny 2, K.H. Burrell 5, M. De Baar

More information

GA A23430 ADVANCED TOKAMAK PHYSICS IN DIII D

GA A23430 ADVANCED TOKAMAK PHYSICS IN DIII D GA A343 ADVANCED TOKAMAK PHYSICS IN DIII D by C.C. PETTY, T.C. LUCE, P.A. POLITZER, M.R. WADE, S.L. ALLEN, M.E. AUSTIN, B. BRAY, K.H. BURRELL, T.A. CASPER, M.S. CHU, J.R. FERRON, E.D. FREDRICKSON, A.M.

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

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

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL.

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 16th IAEA Fusion Conference

More information

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Transport Improvement Near Low Order Rational q Surfaces in DIII D Transport Improvement Near Low Order Rational q Surfaces in DIII D M.E. Austin 1 With K.H. Burrell 2, R.E. Waltz 2, K.W. Gentle 1, E.J. Doyle 8, P. Gohil 2, C.M. Greenfield 2, R.J. Groebner 2, W.W. Heidbrink

More information

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of

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

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D GA A25445 TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D by J.G. WATKINS, T.E. EVANS, C.J. LASNIER, R.A. MOYER, and D.L. RUDAKOV JUNE 2006 QTYUIOP DISCLAIMER This report was prepared

More information

GA A27910 THE SINGLE-DOMINANT MODE PICTURE OF NON-AXISYMMETRIC FIELD SENSITIVIITY AND ITS IMPLICATIONS FOR ITER GEOMETRIC TOLERANCES

GA A27910 THE SINGLE-DOMINANT MODE PICTURE OF NON-AXISYMMETRIC FIELD SENSITIVIITY AND ITS IMPLICATIONS FOR ITER GEOMETRIC TOLERANCES GA A279 THE SINGLE-DOMINANT MODE PICTURE OF NON-AXISYMMETRIC FIELD SENSITIVIITY AND ITS IMPLICATIONS FOR ITER by C. PAZ-SOLDAN, K.H. BURRELL, R.J. BUTTERY, J.S. DEGRASSIE, N.M. FERRARO, A.M. GAROFALO,

More information

27th IAEA Fusion Energy Conference Ahmedabad, India. October 22 27, 2018

27th IAEA Fusion Energy Conference Ahmedabad, India. October 22 27, 2018 Advances in Runaway Electron Control and Model Validation for ITER by C. Paz-Soldan1 with contributions from: N. Eidietis,1 E. Hollmann,2 A. Lvovskiy,3 C. Cooper,3 J. Herfindal,4 R. Moyer,2 D. Shiraki,4

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

Progress in Modeling of ARIES ACT Plasma

Progress in Modeling of ARIES ACT Plasma Progress in Modeling of ARIES ACT Plasma And the ARIES Team A.D. Turnbull, R. Buttery, M. Choi, L.L Lao, S. Smith, General Atomics H. St John, G. Staebler C. Kessel Princeton Plasma Physics Laboratory

More information

MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade

MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade EUROFUSION WPMST1-CP(16) 15178 V Igochine et al. MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade Preprint of Paper to be submitted for publication in Proceedings of 26th

More information

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod JUST DID IT. J A Snipes, N Basse, C Boswell, E Edlund, A Fasoli #, N N Gorelenkov, R S Granetz, L Lin, Y Lin, R Parker, M Porkolab, J

More information

MHD. Jeff Freidberg MIT

MHD. Jeff Freidberg MIT MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium

More information

Kinetic calculation of the resistive wall mode and fishbone-like

Kinetic calculation of the resistive wall mode and fishbone-like inetic calculation of the resistive wall mode and fishbone-like mode instability in tokamak G.Z. Hao 1,2, S.X. Yang 3, Y.Q. Liu 4,2, Z.X. Wang 3, a, A.. Wang 2, and H.D. He 2 1 University of California,

More information

Lecture9: Plasma Physics 1. APPH E6101x Columbia University

Lecture9: Plasma Physics 1. APPH E6101x Columbia University Lecture9: Plasma Physics 1 APPH E6101x Columbia University Last Lecture Force balance (equilibrium) in a magnetized plasma Z-pinch θ-pinch screw-pinch (straight tokamak) Grad-Shafranov Equation - Conservation

More information

Measurement and modeling of three-dimensional equilibria in DIII-D

Measurement and modeling of three-dimensional equilibria in DIII-D Measurement and modeling of three-dimensional equilibria in DIII-D M. J. Lanctot, H. Reimerdes, A. M. Garofalo, M. S. Chu, J. M. Hanson et al. Citation: Phys. Plasmas 18, 056121 (2011); doi: 10.1063/1.3593009

More information

Development in DIII D Tokamak Hybrid Operation Scenarios

Development in DIII D Tokamak Hybrid Operation Scenarios Development in Tokamak Hybrid Operation Scenarios by R.J. Jayakumar in collaboration with M.R. Wade, T.C. Luce, P.A. Politzer, A.W. Hyatt, J.R. Ferron, C.M. Greenfield, E.H. Joffrin, M. Murakami, C.C.

More information