2005, M.Maraschek, IPP-Garching. ASDEX Upgrade

Size: px
Start display at page:

Download "2005, M.Maraschek, IPP-Garching. ASDEX Upgrade"

Transcription

1 ASDEX Upgrade Max-Planck-Institut für Plasmaphysik Control of core MHD Instabilities by ECCD in ASDEX Upgrade M. Maraschek (), G. Gantenbein (), S. Günter (), F. Leuterer (), A. Mück (), A. Manini (), H. Zohm (), and the ASDEX Upgrade-Team () () Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstr., D-8748 Garching, Germany () Institut für Plasmaforschung, Pfaffenwaldring, D-769, Stuttgart, Germany Introduction and motivation Sawtooth tailoring / avoidance with co / counter ECCD NTM stabilisation with co-eccd Deposition width scan Modulated ECCD Early application of ECCD FIR-NTMs and their triggering with ECCD Summary and future plans, M.Maraschek, IPP-Garching

2 Resonant surfaces and MHD modified with ECRH / ECCD #9,.99 s deposition q=, (flat or reversed in the centre in adv. scen.): sawteeth, fast particle driven fishbones, (/)-modes sawtooth tailoring avoidance of NTM trigger burn control q=4/: (4/) NTM, ideal (4/) modes during FIR-NTM artificially trigger / avoid (4/) FIR-NTM transition q=/: (/) NTM stabilisation and suppression of (/)-NTM ECRH beam ECRH deposition layer, controlled by Bt q=: (/) NTM, (/) classical current driven tearing modes stabilisation and suppression of (/)-NTM (j, ne, Te) profile tailoring for advanced scenarios control of current drive and depostion by Bt and toroidal and poloidal launching angle, M.Maraschek, IPP-Garching

3 typical "natural" time-development of an NTM PNI # W.E+7 E+7.4 E+6 βn βonset βsat βcrit W/ t [a.u.]. βp/lp FIR-NTM MRM:MPR() ρp=.6, m= 4 4 time (s) W [cm]. 4 βp,crit : onset at βp,onset > βp,crit, + a seed-island, such as sawteeth : growth to saturated size, proportional to βp,sat FIR-NTM phases at βn >. stabilisation experiments with ECCD : reduction of βp by heating until βp,crit is reached 4: βp = βp,crit, mode decouples from βp : βp < βp,crit for all times mode decays away again βp,sat βp,onset W [a.u] Wsat βp Wsat(FIR,ECCD) < βp, M.Maraschek, IPP-Garching

4 Sawtooth tailoring with ECRH / ECCD collaboration with T.P.Goodman, O.Sauter (CRPP) normalised sawtooth period τ τo HFS PNBI = MW PECCD.4MW co-eccd inversion radius complete stabilization LFS ECR deposition in ρpol co-eccd: - stabilisation / full suppression outside inversion radius - destabilisation for on-axis explainable with critical shear criterium: dq/dr r/q > (dq/dr r/q)crit pure heating (= % co and counter-eccd): - similar behaviour as for co-eccd, but less pronounced counter-eccd: - stabilisation for on-axis - inverse behaviour - effect on (/) mode plays an additional role impurity and He removal burn control in the core, M.Maraschek, IPP-Garching A.Mück, EPS, St.Petersburg A.Mück, PPCF,

5 Optimization of sawtooth tailoring by varying the deposition width. Wide ECCD ρ inv MSE ρ q= P ECH =7kW co-eccd cnt-eccd Bt-ramps PNBI = MW. Narrow ECCD ρ inv MSE ρ q= P ECH =7kW co-eccd cnt-eccd NBI τ / < τ saw saw >.. τ / < τ NBI saw saw > ρ.. ECCD.. ρ.. ECCD critical shear criterium can explain general behaviour clearest impact on τst for narrow deposition, especially for counter-eccd heating effect similar to co-eccd heating always present and stronger for broad deposition (> counter-eccd) jeccd or IECCD/d more important than total IECCD co-eccd more efficient for sawtooth tailoring, M.Maraschek, IPP-Garching A.Mück, PPCF, A.Manini, nd EPS, Tarragona

6 High power NBI experiments: NTM avoidance at high βn =.8 collaboration with T.P.Goodman, O.Sauter (CRPP) #78, counter-eccd NBI *ECR βn (/)-NTM amplitude #7, co-eccd W e6 ECE time (s) 8e6 4e ev 4 higher PNBI = MW to reach NTM-threshold βn.8 fixed by βp feedback sawtooth tailoring less clear with higher PNBI MW off-axis co-eccd no NTM during ECCD no sawteeth, first large sawtooth triggers on-axis counter-eccd fishbone triggered NTM during ECCD (/) mode further outside, no big seed-island NTM avoidance achieved, M.Maraschek, IPP-Garching A.Mück, EPS, St.Petersburg

7 (/)-NTM stabilisation with narrow co-eccd at reduced q9 at βn =.7 PNI = MW * PECCD = MW ( gyrotr.) #97. MW.. BT (/) ampl.. βn βn, Beta Normalized = q time (s) complete stabilisation at βn =.7 with PECCD = MW and PNBI = MW, ITER relev. q9 =.8 βn / PECCD =.7/MW, M.Maraschek, IPP-Garching Bt = -.6T q9 = T Bt =.T Ip =.MA q9 =.8 higher βn βn increase with more PNBI even higher βn achievable (re-excitation, Shafranov-shift)

8 Influence of the deposition width on the (/)-NTM stabilisation Jeccd [MA/m^] φ = -. Ieccd = 7.9 ka, d =.4 cm I/d = 878 ka/m jeccd =.66 MA/m^ φ = -. Ieccd =. ka, d =.9 cm I/d = ka/m jeccd =.66 MA/m^ φ = -. Ieccd =. ka, d =.6 cm I/d = 9 ka/m jeccd =.86 MA/m^ #9,./.9/.66s Peccd =. MW 4 GHz,. MW, θ = -. ρp I/d/PECCD/(Te/ne) [ka/m/mw/kev*e9m^-] peaking of driven current q tor. angle [deg] Wmin / Wsat narrow depostion: I / d = current density maximal for - (TORBEAM) full stabilisation with reduced PECCD / PNBI possible higher βn achievable at stabilisation ( βn / PECCD, βn / (PECCD/PNBI) ) W < d reduces the stabilisation efficiency ECCD modulated by mode (only O-point) might be required for ITER (further modulation experiments will be performed in 6), M.Maraschek, IPP-Garching

9 Stabilisation efficiency as function of deposition width and driven current. βn/peccd [/MW] , M.Maraschek, IPP-Garching I/d/PECCD/(Te/ne) [ka/m/mw/kev*e9m^-] peaking of driven current q9 variation reason for some scatter PECCD might be larger than required for stabilisation (PECCD > PECCD,marginal) the figure of merrit βn / PECCD gives the achievable βn at the stabilisation βn / PECCD "maximum" at maximal current peaking I/d similar improvement achieved for (/)-NTM

10 (/)-NTM stabilisation with broad ECCD (9 ) at early and late application collaboration with A.Lazaros, E.Westerhof (FOM) PECRH PNBI #8 #8 MW.. PNBI = MW PECCD =.7MW βn? βn comparable Bt = -.9T from Bt-scan W % time (s).6s delay of mode onset, with identical fishbone activity (B/f)... mode amplitude comparable due to β-drop power requirement for subsequent stabilisation not resolved more peaked deposition I/d gave no clear answers, M.Maraschek, IPP-Garching

11 Stabilisation of NTMs by non-modulated ECCD (intermediate width) P ECRH modulated: 4kW non-mod.: 8 kw Experiment ECRH Power (not calibrated) #8 MW.. I /I ECCD p odd n db dt even n n=, amplitude n= amplitude non-modulated β N modulated time (s) H. Zohm et al. NF 9 (999) d / W stabilisation also effective for non-modulated current drive for d < W, but: for W d the required current increases significantly for non-modulated ECCD, compared to modulated ECCD, M.Maraschek, IPP-Garching Q.Yu, PoP 4

12 NTM stabilisation with modulated broad ECCD PECRH PNBI #44 W.E+7 E+7 E+6. βn, Beta Normalised. PECRH E+6 (/) NTM amplitude time (s), M.Maraschek, IPP-Garching (/) NTM width reduction of island size, βn recovery phasing correct, but DC gives similar behaviour FIR-NTM phase at βn =.8 yet no clear answer possible, PECCD too small

13 FIR-NTMs - a general NTM behaviour for βn >. collaboration with D.F.Howell (UKAEA) W W. smooth open = ASDEX Upgrade full = JET even n -.. #87 n= amplitude. f (khz). 4 (4,) odd n (,). FIR 7. (,) amplitude (,)... β N,onset t (s) common behaviour of FIR-NTM for βn >. for JET and ASDEX Upgrade stabilility of required coupled ideal (4/)-mode (high p, low q infernal mode) ELMs have a similar effect at JET for βn >.9 for low Bt, low q9 presence of q= surface modifies behaviour in improved H-mode, M.Maraschek, IPP-Garching

14 Triggering / suppressing of FIR-NTMs with ECCD PNBI [MW] (4/) burst w [a.u.] w [a.u.] 4 4 PECRH [MW] βn - feedback controlled ctr-eccd (,) mode amplitude co-eccd (,) mode amplitude time (s) f [khz] #79, SXR:C:... time [s] triggering of ideal pressure driven (4/) mode by q-flattening with ECCD (ideal: growth time, duration; p, q - dependence as for infernal modes) FIR behaviour of NTM at lower / higher βn can be triggered / suppressed control of FIR-NTM feasible complete stabilisation main target, M.Maraschek, IPP-Garching

15 Present status and plans for the future feed-forward Bt - scan feedback stabilisation: () realtime detection of (m/n) mode, its localisation and deposition of the ECCD () feedback loop for the resonant surface (ρeccd = ρntm) () steerable ECCD launchers and tunable gyrotrons immediate reaction at still small island efficiency? PNBI increase to raise βn keep ECCD on q-surface without an NTM ultimate goal is not only removal, but avoidance of NTM feedback loop on ρeccd = ρ(q) with equilibrium q-profile seed-island avoidance (such as sawteeth and/or fishbones) co-eccd to "prevent" bootstrap hole at the resonant surface global tailoring of the j-profile ( effect) or the ne-profile (bootstrap is driving term via ne) to reduce drive for MHD mode, M.Maraschek, IPP-Garching

16 Detection of mode and ECCD on ECE (SENSOR) Radius [m]. cut-off Shot #74, NTM and ECRH position determination by correlation analysis Noise: ELMs NTM position detection ECRH position detection ECRH position detection ECRH position simulation NTMs can be directly measured from high time and radial resolution ECE ECCD modulation (9%) mode can be detected at the same time on ECE input quantities for NTM feedback stabilisation available.89 NBI Power (MW) ECRH Power (MW) Magnetic Perturbation (a.u.) #74 W W.. - high time resolution - realtime capabilities - Toroidal Field T Normalised Beta time (s), M.Maraschek, IPP-Garching. A.Keller, EPS, St. Petersburg

17 The new ECRH system on ASDEX Upgrade (ACTOR) power: 4 MW, provided by 4 gyrotrons pulse length: sec frequency: / 4 GHz as a -f-gyrotron / 7 / 7 / 4 GHz as a step tunable gyrotron change of frequency between pulses launcher: feedback controled deposition via poloidal launching angle toroidal angle can be set between pulses heating and current drive, in particular for advanced tokamak regime suppression of tearing modes control of transport and pressure profile, M.Maraschek, IPP-Garching

18 Summary and outlook local co / counter-eccd has been shown to be a powerful tool to control core MHD narrow deposition layer, well controlable deposition and width sawtooth tailoring at intermediate PNBI, deposition width, NTM avoidance at high PNBI deposition width scan I/d, βn/peccd narrow deposition reduces required power (NTM,sawteeth) early ECCD delays NTM onset modulation of ECCD, no clear answer yet trigger and suppress FIR-NTM physical understanding Outlook: application of feedforward technique: deposition width and modulation experiments extension for more general scenarios (ITER hybrid scenario) realtime feedback control with increased ECCD power and control capabilities will be applied in 6 for stabilisation and avoidance, M.Maraschek, IPP-Garching

19 possible routes to influence NTMs by ECCD sawtooth tailoring / avoidance of seed-island / NTM avoidance reduced size, trigger q= early ECCD q = m/n [A.Mück, NF, ] triggering transition to FIR-NTM, M.Maraschek, IPP-Garching βn βp/lp βonset PNI FIR-NTM # MRM:MPR() ρp=.6, m= 4 4 time (s) W.E+7 reduce magn. shear for (4/)-mode q=4/ active stabilization [S.Günter, PPCF, 4] of saturated island deposition width / island width modulation required for ITER? reduced requirements for early ECCD? (W < Wsat) q = m/n [G.Gantenbein, PRL, ] βsat βcrit E+7 E+6 W [cm]

20 Dependence of the sawtooth frequency on the NBI selection SXR C #667 W/m** variation of tangency radius governs the fast particle distribution from NBI fast particle stabilisation sawtooth period [ms] S S7 S4 S8 S S6 S S time (s) SXR B # time (s) variation in the particle energy between kev and 6 kev has an additional impact significantly different deposition profiles for different sources correction for sawtooth frequency required!, M.Maraschek, IPP-Garching

21 Sawtooth tailoring with ECRH / ECCD collaboration with T.P.Goodman, O.Sauter (CRPP) normalised sawtooth period τ τo normalised sawtooth period τ τo HFS HFS co-eccd inversion radius complete stabilization ECR deposition in ρpol inversion radius complete ST prevention ctr-eccd ECR deposition in ρpol PNBI = MW PECCD.4MW, M.Maraschek, IPP-Garching LFS LFS co-eccd: - stabilisation / full suppression outside inversion radius - destabilisation for on-axis explainable with critical shear criterium: dq/dr r/q > (dq/dr r/q)crit pure heating (= % co and counter-eccd): - similar behaviour as for co-eccd, but less pronounced - addtional stabilisation when (/) mode is directly hit counter-eccd: - stabilisation for on-axis - effect on (/) mode plays an additional role impurity and He removal burn control in the core A.Mück, EPS, St.Petersburg A.Mück, PPCF,

22 Modelling the effect of co-eccd / conter-eccd / pure ECRH on sawteeth COUNTER CD ECRH CO CD. τ ST [ms] ρ dep max ρ(q = ).8.6 ρ.4 modelling of the sawtooth period for pure (!) ECCD and ECRH sweep of the deposition layer over the q= surface ρ dep sweep time [s] heating effect similar to co-eccd with comparable size and broader effect small counter-eccd (braod dep.) effect can be understood in the experiment, M.Maraschek, IPP-Garching C.Angioni, NF 4 (), p.4

23 Power dependence of the sawtooth behaviour MW.6 MW.4 MW.8 SXR B. SXR B co-eccd. SXR B. co-eccd co-eccd ρpol ~ time (s) ρpol ~ time (s) time (s), M.Maraschek, IPP-Garching #67 #67 #679 W/m** W/m** W/m** Frequency [Hz] W/m variation of (/) ampl. with constant sawteeth (/) mode survives role of the (/) mode SXR B ECR time (s) ρpol~. #847 signal: B, index: A.Mück, PPCF,

24 (/)-NTM stabilisation with narrow co-eccd at βn =.6 PNI =.MW * PECCD = MW ( gyrotr.) MW #9 BT complete (/)-stabilisation T βn, Beta Normalized B[a.u.] (/) NTM amplitude time (s) complete stabilisation at βn =.6 with PECCD = MW and PNBI =.MW βn / PECCD =.6/MW βn increase with more PNBI not considered even higher βn achievable (re-excitation), M.Maraschek, IPP-Garching

25 (/)-NTM stabilisation at low q9 =.4 PNBI PECCD =.MW * PECRH #97 MW... βn =.. q9 = W = MOD () EvenN Bt time (s) T - -. Bt =.T, Ip =.MA, higher βn (narrow ECCD deposition) at more ITER relev. q9, but no complete stabilisation achieved, due to lower Te and less driven current, M.Maraschek, IPP-Garching

26 (/)-NTM stabilisation with narrow co-eccd at βn =. MW PNI = MW * PECCD =.4MW (4 gyrotr.) #944 BT complete (/)-stabilisation T - -. (/) NTM amplitude (n=) βn, Beta Normalized time (s). B [a.u.] - V. Locked Mode signal -. stabilisation at βn =. [.9] with PECCD =.4MW [.9MW], PNBI = MW [6.MW] βn / PECCD =.64/MW [./MW] stabilisation of the (/) NTM requires more power (βp,marg, less current drive) faster unlocking of (/)-NTM injection in the O-point of the locked mode works, M.Maraschek, IPP-Garching

27 stabilisation efficiency as function of deposition width, driven current,... I/d/PECCD/(Te/ne) [ka/m/mw/kev*e9m^-] βn/peccd [/MW] q tor. angle [deg] Wmin / Wsat q9 variation reason for some scatter for complete stabilisation PECCD might be to large (PECCD > PECCD,marginal, IECCD > IECCD,marginal) the figure of merrit βn / PECCD gives the achievable βn at the stabilisation βn / PECCD "maximum" at maximal I/d, M.Maraschek, IPP-Garching

28 Nonlinear modelling allows separation of different terms relative island width w/a.. shift of deposition radius during Bt-scan at cm/s (,), (6,4) and (,) component together (,) comp. (,) comp. time dependent Fokker-Planck code to calculate jeccd(r,t) [G. Giruzzi et al.,nf,9(),7(999)] nonlinear D-MHD (circular cylinder) [Q. Yu and S. Günter, POP,7, ()].... time [s] typically -% of plasma current driven at resonant surface (Fokker-Planck-Code) Modelling of DC co-eccd with scan of deposition and Fourier analysis : helical current ((,)-comp.) and -effect ((,)-comp.) are of similar importance complete stabilisation only due to synergy of both effects, M.Maraschek, IPP-Garching

29 Stabilization of neoclassical modes by non-modulated current drive non-modulated co-eccd (AUG) w /a Numerical modelling ECCD #7 ECRH Power x (MW) NBI Power (MW) 8... counter-cd Mirnov even n Mirnov even n n= Amplitude (a.u.) Shift of EC Resonance (cm).6 Stored energy time (s) non-modulated counter-eccd (AUG) n= Amplitude (a.u.).6 Stored energy time (s), M.Maraschek, IPP-Garching I /I =. ECCD P co-cd.... relative island width w/a stabilisation due to synergy of helical current and change in.. shift of deposition radius at cm/s (,), (6,4) and (,) component only (,) component.... time [s] t / τ R

30 Stabilisation of NTMs by non-modulated ECCD (intermediate width) P ECRH odd n db dt even n β N Experiment ECRH Power (not calibrated) #8 n=, amplitude n= amplitude ac: 4kW dc: 8 kw MW time (s) H. Zohm et al. NF 9 (999) w /a Numerical modelling modulated CD ECCD non-modulated CD I /I =.4 ECCD P t= w ECCD /a = (including heat transport and current diffusion) Q. Yu, S. Günter, PPCF 4 (998) 977 t / τ R modulated ECCD in O-point: PECCD/PNI 4-8%, 4% βn recovery with mode reduction stabilisation also effective for non-modulated current drive for d < W, M.Maraschek, IPP-Garching

31 Stabilisation of NTMs by non-modulated ECCD (intermediate width) P ECRH odd n db dt even n β N modulated: 4kW non-mod.: 8 kw Experiment ECRH Power (not calibrated) #8 n=, amplitude n= amplitude MW time (s) H. Zohm et al. NF 9 (999) PECCD [kw] W B [a.u.].. dw/dt [a.u.] #8 modulated ECCD in O-point: PECCD/PNI 4-8%, 4% βn recovery with mode reduction stabilisation also effective for non-modulated current drive for d < W clearly highest reduction rate at early modulated phase, M.Maraschek, IPP-Garching time [s]

32 phase adjustment of the modulated ECCD B = MHD GYRTRIGi #44 V -. D = MHD GYRTRIG V I = E+F+G+H; E time (s) correct phase adjustment for modulated deposition from the equilibrium ECCD is capable for modulation with f = khz requirement for ITER for W > d?, M.Maraschek, IPP-Garching

33 FIR-NTMs by nonlinear mode coupling with(m+,n+) modes and (,) mode even n f (khz) #87 n= amplitude. (,) amplitude odd n (4,) (,) (,) t (s) presence of both (m+/n+) mode and (/) mode required (,) amplitude (a.u.) f (khz) (4,) (,) t (s) # 68. f(,) f(,) phase locked resonance required, M.Maraschek, IPP-Garching A.Gude, Nucl. Fusion 4 () 8

34 Triggering / suppressing of FIR-NTMs with ECCD NBI heating power [MW] ECRH [MW] NBI heating power [MW] w [a.u.] w [a.u.] toroidal magnetic field β N ctr-eccd co-eccd ctr-eccd co-eccd (,) amplitude (,) amplitude.... Time (s) w [a.u.] w [a.u.] 4 4 β N ECRH power [MW] ctr-eccd (,) mode amplitude co-eccd (,) mode amplitude time (s) triggering of ideal pressure driven (4/) mode by q-flattening with ECCD FIR behaviour of NTM at lower / higher βn can be triggered / suppressed, M.Maraschek, IPP-Garching

35 General idea of a feedback loop for NTM stabilisation NTM detection mode numbers ECCD localisation mode localisation localisation from calibrated / improved equilibrium mode phase ECCD and loop off ECCD and loop on first guess launch angle of ECCD ρntm = ρeccd ECCD modulation NTM amplitude =, βn - max, WMHD = max,... launch angle Rplasma, Bt at DIII-D ECCD deposition meas. by ECE TORBEAM calculations for "first guess" for new scenarios ECCD modulation available trigger, M.Maraschek, IPP-Garching

36 Newly developed tools for the stabilisation (SENSOR) PNI MOD:EvenN PECCD #9 W.E+7 E+7 E amplitude from FFT tracing RVE:MHD low pass from ECCD trigger time (s).8.4 V 8 4 EvenN Trigger detection of odd n ((/)-NTM, but (/) also) and even n ((/)-NTM) diagnostic upgrade provides realtime n=, n=, n= detection detection of localisation of the mode and ECCD via realtime ECE / SXR, M.Maraschek, IPP-Garching

IAEA-CN-116 / EX / 7-2

IAEA-CN-116 / EX / 7-2 ASDEX Upgrade Max-Planck-Institut für Plasmaphysik Active Control of MHD Instabilities by ECCD in ASDEX Upgrade M. Maraschek (), G. Gantenbein (), T.P. Goodman (3), S. Günter (), D.F. Howell (4), F. Leuterer

More information

EXW/10-2Ra. Avoidance of Disruptions at High β N in ASDEX Upgrade with Off-Axis ECRH

EXW/10-2Ra. Avoidance of Disruptions at High β N in ASDEX Upgrade with Off-Axis ECRH 1 EXW/1-2Ra Avoidance of Disruptions at High β N in ASDEX Upgrade with Off-Axis ECRH B. Esposito 1), G. Granucci 2), M. Maraschek 3), S. Nowak 2), A. Gude 3), V. Igochine 3), R. McDermott 3), E. oli 3),

More information

Increased Stable Beta in DIII D by Suppression of a Neoclassical Tearing Mode Using Electron Cyclotron Current Drive and Active Feedback

Increased Stable Beta in DIII D by Suppression of a Neoclassical Tearing Mode Using Electron Cyclotron Current Drive and Active Feedback 1 EX/S1-3 Increased Stable Beta in DIII D by Suppression of a Neoclassical Tearing Mode Using Electron Cyclotron Current Drive and Active Feedback R.J. La Haye, 1 D.A. Humphreys, 1 J. Lohr, 1 T.C. Luce,

More information

PRESENT STATUS OF THE NEW MULTI-FREQUENCY ECRH SYSTEM FOR ASDEX UPGRADE

PRESENT STATUS OF THE NEW MULTI-FREQUENCY ECRH SYSTEM FOR ASDEX UPGRADE Max-Planck-Institut für Plasmaphysik PRESENT STATUS OF THE NEW MULTI-FREQUENCY ECRH SYSTEM FOR ASDEX UPGRADE D. Wagner, G. Grünwald, F. Leuterer, A. Manini, F. Monaco, M. Münich, H. Schütz, J. Stober,

More information

Neoclassical Tearing Mode Control with ECCD and Magnetic Island Evolution in JT-60U

Neoclassical Tearing Mode Control with ECCD and Magnetic Island Evolution in JT-60U EX/5-4 Neoclassical Tearing Mode Control with ECCD and Magnetic Island Evolution in A. Isayama 1), G. Matsunaga 1), T. Kobayashi 1), S. Moriyama 1), N. Oyama 1), Y. Sakamoto 1), T. Suzuki 1), H. Urano

More information

SUPPRESSION OF NEOCLASSICAL TEARING MODES IN THE PRESENCE OF SAWTEETH INSTABILITIES BY RADIALLY LOCALIZED OFF-AXIS

SUPPRESSION OF NEOCLASSICAL TEARING MODES IN THE PRESENCE OF SAWTEETH INSTABILITIES BY RADIALLY LOCALIZED OFF-AXIS SUPPRESSION OF NEOCLASSICAL TEARING MODES IN THE PRESENCE OF SAWTEETH INSTABILITIES BY RADIALLY LOCALIZED OFF-AXIS ELECTRON CYCLOTRON CURRENT DRIVE IN THE TOKAMAK R.. LA HAYE,. LOHR, T.C. LUCE, C.C. PETTY,

More information

Active Control for Stabilization of Neoclassical Tearing Modes

Active Control for Stabilization of Neoclassical Tearing Modes Active Control for Stabilization of Neoclassical Tearing Modes Presented by D.A. Humphreys General Atomics 47th APS-DPP Meeting Denver, Colorado October 24 28, 2005 Control of NTM s is an Important Objective

More information

NTM control in ITER. M. Maraschek for H. Zohm. MPI für Plasmaphysik, D Garching, Germany, EURATOM Association

NTM control in ITER. M. Maraschek for H. Zohm. MPI für Plasmaphysik, D Garching, Germany, EURATOM Association NTM control in ITER M. Maraschek for H. Zohm MPI für Plasmaphysik, D-85748 Garching, Germany, EURATOM Association ECRH in ITER physics of the NTM stabilisation efficiency of the stabilisation gain in plasma

More information

GA A25780 STABILIZATION OF NEOCLASSICAL TEARING MODES IN TOKAMAKS BY RADIO FREQUENCY CURRENT DRIVE

GA A25780 STABILIZATION OF NEOCLASSICAL TEARING MODES IN TOKAMAKS BY RADIO FREQUENCY CURRENT DRIVE GA A25780 STABILIZATION OF NEOCLASSICAL TEARING MODES IN TOKAMAKS by R.J. LA HAYE MAY 2007 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government.

More information

Presented by Rob La Haye. on behalf of Francesco Volpe. at the 4 th IAEA-TM on ECRH for ITER

Presented by Rob La Haye. on behalf of Francesco Volpe. at the 4 th IAEA-TM on ECRH for ITER Locked Neoclassical Tearing Mode Control on DIII-D by ECCD and Magnetic Perturbations Presented by Rob La Haye General Atomics, San Diego (USA) on behalf of Francesco Volpe Max-Planck Gesellschaft (Germany)

More information

Feedback control of ECRH for MHD mode stabilization on TEXTOR

Feedback control of ECRH for MHD mode stabilization on TEXTOR -Institute for Plasma Physics Rijnhuizen Association Euratom- Feedback control of ECRH for MHD mode stabilization on TEXTOR Bart Hennen Tuesday, 25 November, 28 With contributions from: E. Westerhof, M.

More information

RECENT UPGRADES AND EXTENSIONS OF THE ASDEX UPGRADE ECRH SYSTEM

RECENT UPGRADES AND EXTENSIONS OF THE ASDEX UPGRADE ECRH SYSTEM RECENT UPGRADES AND EXTENSIONS OF THE ASDEX UPGRADE ECRH SYSTEM D. Wagner 1, J. Stober 1, F. Leuterer 1, F. Monaco 1, M. Münich 1, D. Schmid-Lorch 1, H. Schütz 1, H. Zohm 1, M. Thumm 2, T. Scherer 3, A.

More information

ECRH Beam Optics Optimization for ITER Upper Port Launcher

ECRH Beam Optics Optimization for ITER Upper Port Launcher ECRH Beam Optics Optimization for ITER Upper Port Launcher H. Shidara 1, M.A. Henderson 1, R. Chavan 1, D. Farina 2, E. Poli 3, G. Ramponi 2 1: CRPP, EURATOM Confédération Suisse, EPFL, CH-1015 Lausanne,

More information

Real time control of the sawtooth period using EC launchers

Real time control of the sawtooth period using EC launchers Real time control of the sawtooth period using EC launchers J I Paley, F Felici, S Coda, T P Goodman, F Piras and the TCV Team Ecole Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique

More information

ICRF Physics in KSTAR Steady State

ICRF Physics in KSTAR Steady State ICRF Physics in KSTAR Steady State Operation (focused on the base line operation) Oct. 24, 2005 Jong-gu Kwak on the behalf of KSTAR ICRF TEAM Korea Atomic Energy Research Institute Contents Roles of ICRF

More information

Experiments with real-time controlled ECW

Experiments with real-time controlled ECW Experiments with real-time controlled ECW on the TCV Tokamak Experiments with real-time controlled ECW on the TCV Tokamak S. Alberti 1, G. Arnoux 2, J. Berrino 1, Y.Camenen 1, S. Coda 1, B.P. Duval 1,

More information

Tearing mode formation induced by internal crash events at

Tearing mode formation induced by internal crash events at Tearing mode formation induced by internal crash events at different β N V. Igochine 1, I. Classen 2, M. Dunne 1, A. Gude 1, S. Günter 1, K. Lackner 1, R. M. McDermott 1, M. Sertoli 1, D. Vezinet 1, M.

More information

RF Heating and Current Drive in the JT-60U Tokamak

RF Heating and Current Drive in the JT-60U Tokamak KPS Meeting, ct. 22 25, Chonju RF Heating and Current Drive in the JT-6U Tokamak presented by T. Fujii Japan Atomic Energy Agency Outline JT-6U 1. JT-6U Tokamak Device and its Objectives 2. LHRF Current

More information

System Upgrades to the DIII-D Facility

System Upgrades to the DIII-D Facility System Upgrades to the DIII-D Facility A.G. Kellman for the DIII-D Team 24th Symposium on Fusion Technology Warsaw, Poland September 11-15, 2006 Upgrades Performed During the Long Torus Opening (LTOA)

More information

NTM Suppression and Avoidance at DIII-D Using Real-time Mirror Steering of ECCD

NTM Suppression and Avoidance at DIII-D Using Real-time Mirror Steering of ECCD NTM Suppression and Avoidance at DIII-D Using Real-time Mirror Steering of ECCD Egemen Kolemen 1, N.W. Eidietis 2, R. Ellis 1, D.A. Humphreys 2, R.J. La Haye 2, J. Lohr 2, S. Noraky 2, B.G. Penaflor 2,

More information

Improved core transport triggered by off-axis ECRH switch-off on the HL-2A tokamak

Improved core transport triggered by off-axis ECRH switch-off on the HL-2A tokamak Improved core transport triggered by off-axis switch-off on the HL-2A tokamak Z. B. Shi, Y. Liu, H. J. Sun, Y. B. Dong, X. T. Ding, A. P. Sun, Y. G. Li, Z. W. Xia, W. Li, W.W. Xiao, Y. Zhou, J. Zhou, J.

More information

Optimization of the ITER EC H&CD Functional Capabilities while Relaxing the Engineering Constraints

Optimization of the ITER EC H&CD Functional Capabilities while Relaxing the Engineering Constraints Optimization of the ITER EC H&CD Functional Capabilities while Relaxing the Engineering Constraints D. Farina, M. Henderson, L. Figini, G. Saibene, T. Goodman, K. Kajiwara, T. Omori, E. Poli, D. Strauss

More information

Recent progress of 170 GHz Gyrotron in KSTAR

Recent progress of 170 GHz Gyrotron in KSTAR Recent progress of 170 GHz Gyrotron in KSTAR Japan-Korea Workshop on Physics and Technology of Heating and Current Drive Hanwha Resort, Haeundae, Busan, Korea January 28-30, 2013 J.H. Jeong, M. Joung,

More information

Max-Planck-Institut für Plasmaphysik

Max-Planck-Institut für Plasmaphysik Max-Planck-Institut für Plasmaphysik STATUS OF THE NEW ECRH SYSTEM FOR ASDEX UPGRADE D. Wagner, G.Grünwald, F.Leuterer, F.Monaco, M.Münich, H.Schütz, F.Ryter, R. Wilhelm, H.Zohm, T.Franke Max-Planck-Institut

More information

Combined Electron Cyclotron Emission And Heating For The Suppression Of Magnetic Islands In Fusion Plasmas

Combined Electron Cyclotron Emission And Heating For The Suppression Of Magnetic Islands In Fusion Plasmas Combined Electron Cyclotron Emission And Heating For The Suppression Of Magnetic Islands In Fusion Plasmas, M.R. de Baar, B.A. Hennen, J.W. Oosterbeek FOM Institute DIFFER - Dutch Institute for Fundamental

More information

Operational progress of 170GHz 1MW ECH system in KSTAR

Operational progress of 170GHz 1MW ECH system in KSTAR 8 th IAEA TM on Steady State Operation of Magnetic Fusion Devices, May. 29, 2015, NARA, JAPAN Operational progress of 170GHz 1MW ECH system in KSTAR J. H. Jeong a, Y. S. Bae a, M. Joung a, M. H. Woo a,

More information

Effect of electrode biasing on m/n=2/1 tearing modes in J-TEXT experiments

Effect of electrode biasing on m/n=2/1 tearing modes in J-TEXT experiments Effect of electrode biasing on m/n=2/1 tearing modes in J-TEXT experiments Hai Liu 1, Qiming Hu 1, a, Zhipeng Chen 1, a, Q. Yu 2, Lizhi Zhu 1, Zhifeng Cheng 1, Ge Zhuang 1 and Zhongyong Chen 1 1 State

More information

EX/P9-5. Comprehensive Control of Resistive Wall Modes in DIII-D Advanced Tokamak Plasmas

EX/P9-5. Comprehensive Control of Resistive Wall Modes in DIII-D Advanced Tokamak Plasmas Comprehensive Control of Resistive Wall Modes in DIII-D Advanced Tokamak Plasmas M. Okabayashi 1), I.N. Bogatu 2), T. Bolzonella 3) M.S. Chance 1), M.S. Chu 4), A.M. Garofalo 4), R. Hatcher 1), Y. In 2),

More information

Advanced Tokamak Program and Lower Hybrid Experiment. Ron Parker MIT Plasma Science and Fusion Center

Advanced Tokamak Program and Lower Hybrid Experiment. Ron Parker MIT Plasma Science and Fusion Center Advanced Tokamak Program and Lower Hybrid Experiment Ron Parker MIT Plasma Science and Fusion Center Alcator C-Mod Program Advisory Meeting 23-24 February 2004 Main Goals of the Alcator C-Mod AT Program

More information

FaDiS, a Fast Switch and Combiner for High-power Millimetre Wave Beams

FaDiS, a Fast Switch and Combiner for High-power Millimetre Wave Beams FaDiS, a Fast Switch and Combiner for High-power Millimetre Wave Beams W. Kasparek, M. Petelin, D. Shchegolkov, V. Erckmann 3, B. Plaum, A. Bruschi 4, ECRH groups at IPP Greifswald 3, FZK Karlsruhe 5,

More information

Advanced Density Profile Reflectometry; the State-of-the-Art and Measurement Prospects for ITER

Advanced Density Profile Reflectometry; the State-of-the-Art and Measurement Prospects for ITER Advanced Density Profile Reflectometry; the State-of-the-Art and Measurement Prospects for ITER by E.J. Doyle With W.A. Peebles, L. Zeng, P.-A. Gourdain, T.L. Rhodes, S. Kubota and G. Wang Dept. of Electrical

More information

TOROIDAL ALFVÉN EIGENMODES

TOROIDAL ALFVÉN EIGENMODES TOROIDAL ALFVÉN EIGENMODES S.E. Sharapov Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, UK OUTLINE OF LECTURE 4 Toroidicity induced frequency gaps and Toroidal

More information

Pedestal Turbulence Dynamics in ELMing and ELM-free H-mode Plasmas

Pedestal Turbulence Dynamics in ELMing and ELM-free H-mode Plasmas Pedestal Turbulence Dynamics in ELMing and ELM-free H-mode Plasmas Z. Yan1, G.R. McKee1, R.J. Groebner2, P.B. Snyder2, T.H. Osborne2, M.N.A. Beurskens3, K.H. Burrell2, T.E. Evans2, R.A. Moyer4, H. Reimerdes5

More information

Electron Bernstein Wave Heating and Emission in the TCV Tokamak

Electron Bernstein Wave Heating and Emission in the TCV Tokamak Electron Bernstein Wave Heating and Emission in the TCV Tokamak A. Mueck 1, Y. Camenen 1, S. Coda 1, L. Curchod 1, T.P. Goodman 1, H.P. Laqua 2, A. Pochelon 1, L. Porte 1, V.S. Udintsev 1, F. Volpe 2,

More information

Recent Results on RFX-mod control experiments in RFP and tokamak configuration

Recent Results on RFX-mod control experiments in RFP and tokamak configuration Recent Results on RFX-mod control experiments in RFP and tokamak configuration L.Marrelli Summarizing contributions by M.Baruzzo, T.Bolzonella, R.Cavazzana, Y. In, G.Marchiori, P.Martin, E.Martines, M.Okabayashi,

More information

Experimental results and Upgrade plan of ECH/CD system in KSTAR

Experimental results and Upgrade plan of ECH/CD system in KSTAR 2015 KSTAR conference, Feb. 27, 2015, Daejeon, Korea Experimental results and Upgrade plan of ECH/CD system in KSTAR J. H. Jeong a, Y. S. Bae a, M. Joung a, J. W. Han a, I. H. Rhee a, I. H. Rhee a, S.

More information

Task on the evaluation of the plasma response to the ITER ELM stabilization coils in ITER H- mode operational scenarios. Technical Specifications

Task on the evaluation of the plasma response to the ITER ELM stabilization coils in ITER H- mode operational scenarios. Technical Specifications Task on the evaluation of the plasma response to the ITER ELM stabilization coils in ITER H- mode operational scenarios Technical Specifications Version 1 Date: 28/07/2011 Name Affiliation Author G. Huijsmans

More information

GA A25836 PRE-IONIZATION EXPERIMENTS IN THE DIII-D TOKAMAK USING X-MODE SECOND HARMONIC ELECTRON CYCLOTRON HEATING

GA A25836 PRE-IONIZATION EXPERIMENTS IN THE DIII-D TOKAMAK USING X-MODE SECOND HARMONIC ELECTRON CYCLOTRON HEATING GA A25836 PRE-IONIZATION EXPERIMENTS IN THE DIII-D TOKAMAK USING X-MODE SECOND HARMONIC ELECTRON CYCLOTRON HEATING by G.L. JACKSON, M.E. AUSTIN, J.S. degrassie, J. LOHR, C.P. MOELLER, and R. PRATER JULY

More information

Abstract. G.D. Garstka 47 th APS-DPP Denver October 27, Pegasus Toroidal Experiment University of Wisconsin-Madison

Abstract. G.D. Garstka 47 th APS-DPP Denver October 27, Pegasus Toroidal Experiment University of Wisconsin-Madison Abstract The PEGASUS Toroidal Experiment provides an attractive opportunity for investigating the physics and implementation of electron Bernstein wave (EBW) heating and current drive in an overdense ST

More information

3D full wave code modelling of ECRF plasma heating in tokamaks and ITER at fundamental and second harmonics

3D full wave code modelling of ECRF plasma heating in tokamaks and ITER at fundamental and second harmonics 3D full wave code modelling of ECRF plasma heating in tokamaks and ITER at fundamental and second harmonics Vdovin V.L. RRC Kurchatov Institute Tokamak Physics Institute vdov@nfi.kiae.ru Abstract We present

More information

Technical Readiness Level For Plasma Control

Technical Readiness Level For Plasma Control Technical Readiness Level For Plasma Control PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION A.D. Turnbull, General Atomics ARIES Team Meeting University of Wisconsin, Madison,

More information

Selected highlights of ECH/ECCD physics studies in the TCV tokamak

Selected highlights of ECH/ECCD physics studies in the TCV tokamak EPJ Web of Conferences 87, 02002( 2015) DOI: 10.1051/ epjconf/ 20158702002 C Owned by the authors, published by EDP Sciences, 2015 Selected highlights of ECH/ECCD physics studies in the TCV tokamak T.P.

More information

ECRF Heating on CS Reactors

ECRF Heating on CS Reactors ECRF Heating on CS Reactors T.K. Mau UC-San Diego With input from L.P. Ku (PPPL), J.F. Lyon (ORNL), X.R. Wang (UCSD) ARIES Project Meeting May 6-7, 2003 Livermore, California 1 OUTLINE ECH scenario studies

More information

SUMMARY OF THE EXPERIMENTAL SESSION EC-10 WORKSHOP

SUMMARY OF THE EXPERIMENTAL SESSION EC-10 WORKSHOP SUMMARY OF THE EXPERIMENTAL SESSION by J. LOHR GENEHL ATUMRCS This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government

More information

High-Resolution Detection and 3D Magnetic Control of the Helical Boundary of a Wall-Stabilized Tokamak Plasma

High-Resolution Detection and 3D Magnetic Control of the Helical Boundary of a Wall-Stabilized Tokamak Plasma 1 EX/P4-19 High-Resolution Detection and 3D Magnetic Control of the Helical Boundary of a Wall-Stabilized Tokamak Plasma J. P. Levesque, N. Rath, D. Shiraki, S. Angelini, J. Bialek, P. Byrne, B. DeBono,

More information

Localization of MHD and fast particle modes using reflectometry in ASDEX Upgrade

Localization of MHD and fast particle modes using reflectometry in ASDEX Upgrade Localization of MHD and fast particle modes using reflectometry in ASDEX Upgrade S da Graça 1, G D Conway 2, P Lauber 2, M Maraschek 2, D Borba 1, S Günter 2, L Cupido 1, K Sassenberg 3, F Serra 1, ME

More information

Lower Hybrid. Ron Parker Alcator C-Mod PAC Meeting January January 2006 Alcator C-Mod PAC Meeting 1

Lower Hybrid. Ron Parker Alcator C-Mod PAC Meeting January January 2006 Alcator C-Mod PAC Meeting 1 Lower Hybrid Ron Parker Alcator C-Mod PAC Meeting 25-27 January 2006 25-27 January 2006 Alcator C-Mod PAC Meeting 1 Goal of Lower Hybrid Current Drive Experiments Use Lower Hybrid Current Drive to supplement

More information

Abstract. heating with a HHFW RF system has begun. This system supplies bulk T(e) heating with

Abstract. heating with a HHFW RF system has begun. This system supplies bulk T(e) heating with Abstract Present experimental campaigns on the are concerned with accessing q- and β-limits in an ultra-low aspect ratio plasma. To date, Pegasus plasma are heated only with an OH solenoid, but an additional

More information

The 10-MW ECR heating and current drive system for W7-X: First gyrotron operates at IPP- Greifswald. In this issue...

The 10-MW ECR heating and current drive system for W7-X: First gyrotron operates at IPP- Greifswald. In this issue... Published by Fusion Energy Division, Oak Ridge National Laboratory Building 5700 P.O. Box 2008 Oak Ridge, TN 37831-6169, USA Editor: James A. Rome Issue 91 March 2004 E-Mail: jar@ornl.gov Phone (865) 482-5643

More information

RF Physics: Status and Plans

RF Physics: Status and Plans RF Physics: Status and Plans Program Advisory Committee meeting February 6-7, 2002 S. J. Wukitch Outline: 1. Overview of RF Physics issues 2. Review of antenna performance and near term modifications.

More information

Observation of Electron Bernstein Wave Heating in the RFP

Observation of Electron Bernstein Wave Heating in the RFP Observation of Electron Bernstein Wave Heating in the RFP Andrew Seltzman, Jay Anderson, John Goetz, Cary Forest Madison Symmetric Torus - University of Wisconsin Madison Department of Physics Aug 1, 2017

More information

Toroidal Geometry Effects in the Low Aspect Ratio RFP

Toroidal Geometry Effects in the Low Aspect Ratio RFP Toroidal Geometry Effects in the Low Aspect Ratio RFP Carl Sovinec Los Alamos National Laboratory Chris Hegna University of Wisconsin-Madison 2001 International Sherwood Fusion Theory Conference April

More information

Helicon mode formation and rf power deposition in a helicon source

Helicon mode formation and rf power deposition in a helicon source Helicon mode formation and rf power deposition in a helicon source Michael Krämer & Kari Niemi Institut für Experimentalphysik II, Ruhr-Universität D-4478 Bochum, Germany Helicon Mini-Conference APS-DPP,

More information

Toroidal Rotation and Ion Temperature Validations in KSTAR Plasmas

Toroidal Rotation and Ion Temperature Validations in KSTAR Plasmas Toroidal Rotation and Ion Temperature Validations in KSTAR Plasmas S. G. Lee 1, H. H. Lee 1, W. H. Ko 1, J. W. Yoo 2, on behalf of the KSTAR team and collaborators 1 NFRI, Daejeon, Korea 2 UST, Daejeon,

More information

PLASMA STUDIES AT HIGH NORMALIZED CURRENT IN THE PEGASUS EXPERIMENT

PLASMA STUDIES AT HIGH NORMALIZED CURRENT IN THE PEGASUS EXPERIMENT PLASMA STUDIES AT HIGH NORMALIZED CURRENT IN THE PEGASUS EXPERIMENT for the PEGASUS team: D. Battaglia M. Bongard S. Burke N. Eideitis G. Garstka M. Kozar B. Lewicki E. Unterberg Raymond.J. Fonck presented

More information

Conceptual Design of Magnetic Island Divertor in the J-TEXT tokamak

Conceptual Design of Magnetic Island Divertor in the J-TEXT tokamak The 2 nd IAEA Technical Meeting on Divertor Concepts, 13 to 16 November, 2017, Suzhou China Conceptual Design of Magnetic Island Divertor in the J-TEXT tokamak Bo Rao 1, Yonghua Ding 1, Song Zhou 1, Nengchao

More information

The Compact Toroidal Hybrid A university scale fusion experiment. Greg Hartwell

The Compact Toroidal Hybrid A university scale fusion experiment. Greg Hartwell The Compact Toroidal Hybrid A university scale fusion experiment Greg Hartwell Plasma Physics Workshop, SMF-PPD, Universidad National Autónoma México, October 12-14, 2016 CTH Team and Collaborators CTH

More information

First Operations of the Real-Time ECRH/ECCD System for Control of Magnetohydrodynamics Instabilities in the FTU Tokamak

First Operations of the Real-Time ECRH/ECCD System for Control of Magnetohydrodynamics Instabilities in the FTU Tokamak 1 EX P6 04 First Operations of the Real-Time ECRH/ECCD System for Control of Magnetohydrodynamics Instabilities in the FTU Tokamak C. Sozzi 1, E. Alessi 1, L. Boncagni 2, C. Galperti 1, C. Marchetto 1,

More information

INITIAL RESULTS FROM THE MULTI-MEGAWATT 110 GHz ECH SYSTEM FOR THE DIII D TOKAMAK

INITIAL RESULTS FROM THE MULTI-MEGAWATT 110 GHz ECH SYSTEM FOR THE DIII D TOKAMAK GA A22576 INITIAL RESULTS FROM THE MULTI-MEGAWATT 110 GHz ECH SYSTEM by R.W. CALLIS, J. LOHR, R.C. O NEILL, D. PONCE, M.E. AUSTIN, T.C. LUCE, and R. PRATER APRIL 1997 This report was prepared as an account

More information

National Fusion Research Institute a. Princeton Plasma Physics Laboratory

National Fusion Research Institute a. Princeton Plasma Physics Laboratory Ko-Ja Workshop on Physics and Technology of Heating and Current Drive, Pohang, Korea, 2016 M. Joung, J. H. Jeong, J. W. Han, I. H. Lee, S. K. Kim, S. J. Wang, J. G. Kwak, R. Ellis a, J. Hosea a and the

More information

Heating Issues. G.Granucci on behalf of the project team

Heating Issues. G.Granucci on behalf of the project team Heating Issues G.Granucci on behalf of the project team EURO fusion DTT Workshop Frascati, Italy, 19-20 June 2017 Summary Physical Requirements DTT Heating Mix ECRH System ICRH System Auxiliary Heating

More information

High-power microwave diplexers for advanced ECRH systems

High-power microwave diplexers for advanced ECRH systems High-power microwave diplexers for advanced ECRH systems W. Kasparek 1, M. Petelin 2, V. Erckmann 3, A. Bruschi 4, F. Noke 3, F. Purps 3, F. Hollmann 3, Y. Koshurinov 2, L. Lubyako 2, B. Plaum 1, W. Wubie

More information

ICRF Operation with Improved Antennas in a Full W-wall ASDEX Upgrade, Status and Developments

ICRF Operation with Improved Antennas in a Full W-wall ASDEX Upgrade, Status and Developments 1 EX/P5-19 ICRF Operation with Improved Antennas in a Full W-wall ASDEX Upgrade, Status and Developments V. Bobkov 1*, M. Balden 1, F. Braun 1, R. Dux 1, A. Herrmann 1, H. Faugel 1, H. Fünfgelder 1, L.

More information

Development in Russia of Megawatt Power Gyrotrons for Fusion

Development in Russia of Megawatt Power Gyrotrons for Fusion 1 ITR/1-4Ra Development in Russia of Megawatt Power Gyrotrons for Fusion A.G.Litvak 1, G.G.Denisov 1, V.E.Myasnikov 2, E.M.Tai 2,E.V. Sokolov, V.I.Ilin 3. 1 Institute of Applied Physics Russian Academy

More information

Feedback control on EXTRAP-T2R with coils covering full surface area of torus

Feedback control on EXTRAP-T2R with coils covering full surface area of torus Active control of MHD Stability, Univ. Wisconsin, Madison, Oct 31 - Nov 2, 2005 Feedback control on EXTRAP-T2R with coils covering full surface area of torus presented by Per Brunsell P. R. Brunsell 1,

More information

Experimental observations of plasma edge magnetic field response to resonant magnetic

Experimental observations of plasma edge magnetic field response to resonant magnetic Home Search Collections Journals About Contact us My IOPscience Experimental observations of plasma edge magnetic field response to resonant magnetic perturbation on the TEXTOR Tokamak This article has

More information

Helicon Wave Current Drive in KSTAR Plasmas

Helicon Wave Current Drive in KSTAR Plasmas Daejeon Helicon Wave Current Drive in KSTAR Plasmas S. J. Wanga, H. J. Kima, Jeehyun Kima, V. Vdovinb, B. H. Parka, H. H. Wic, S. H. Kimd, and J. G. Kwaka anational Fusion Research Institute, Daejeon,

More information

Non-inductive Production of Extremely Overdense Spherical Tokamak Plasma by Electron Bernstein Wave Excited via O-X-B Method in LATE

Non-inductive Production of Extremely Overdense Spherical Tokamak Plasma by Electron Bernstein Wave Excited via O-X-B Method in LATE 1 EXW/P4-4 Non-inductive Production of Extremely Overdense Spherical Tokamak Plasma by Electron Bernstein Wave Excited via O-X-B Method in LATE H. Tanaka, M. Uchida, T. Maekawa, K. Kuroda, Y. Nozawa, A.

More information

AUTOMATIC REAL-TIME TRACKING AND STABILIZATION OF MAGNETIC ISLANDS IN A TOKAMAK BY ECCD/ECRH

AUTOMATIC REAL-TIME TRACKING AND STABILIZATION OF MAGNETIC ISLANDS IN A TOKAMAK BY ECCD/ECRH AUTOMATIC REAL-TIME TRACKING AND STABILIZATION OF MAGNETIC ISLANDS IN A TOKAMAK BY ECCD/ECRH Enzo Lazzaro, J. O. Berrino, S. Cirant, G. D Antona, F.Gandini,G.Granucci and F.Iannone 1 Outline Summary of

More information

Sensitivity study for the optimization of the viewing chord arrangement of the ITER poloidal polarimeter

Sensitivity study for the optimization of the viewing chord arrangement of the ITER poloidal polarimeter P8-29 6th International Toki Conference, December 5-8, 26 Sensitivity study for the optimization of the viewing chord arrangement of the ITER poloidal polarimeter T. Yamaguchi, Y. Kawano and Y. Kusama

More information

Effect of ICRF Mode Conversion at the Ion-Ion Hybrid Resonance on Plasma Confinement in JET

Effect of ICRF Mode Conversion at the Ion-Ion Hybrid Resonance on Plasma Confinement in JET EFDA JET CP()- A.Lyssoivan, M.J.Mantsinen, D.Van Eester, R.Koch, A.Salmi, J.-M.Noterdaeme, I.Monakhov and JET EFDA Contributors Effect of ICRF Mode Conversion at the Ion-Ion Hybrid Resonance on Plasma

More information

C-Mod ICRF Program. Alcator C-Mod PAC Meeting January 25-27, 2006 MIT Cambridge MA. Presented by S.J. Wukitch

C-Mod ICRF Program. Alcator C-Mod PAC Meeting January 25-27, 2006 MIT Cambridge MA. Presented by S.J. Wukitch C-Mod ICRF Program Alcator C-Mod PAC Meeting January 5-7, 006 MIT Cambridge MA Presented by S.J. Wukitch Outline: 1. Overview of ICRF program. Antenna performance evaluation and coupling 3. Mode conversion

More information

Observation of high-frequency secondary modes during strong tearing mode activity in FTU plasmas without fast ions

Observation of high-frequency secondary modes during strong tearing mode activity in FTU plasmas without fast ions 1 Observation of high-frequency secondary modes during strong tearing mode activity in FTU plasmas without fast ions P.Buratti, P.Smeulders, F. Zonca, S.V. Annibaldi, M. De Benedetti, H. Kroegler, G. Regnoli,

More information

Locked-mode avoidance and recovery without external momentum input using Ion Cyclotron Resonance Heating

Locked-mode avoidance and recovery without external momentum input using Ion Cyclotron Resonance Heating 1 EX/P4-39 Locked-mode avoidance and recovery without external momentum input using Ion Cyclotron Resonance Heating L. F. Delgado-Aparicio 1, J. E. Rice 2, E. Edlund 2, I. Cziegler 3, L. Sugiyama 4, D.

More information

DIII D Quiescent H-Mode Experiments with Co Plus Counter Neutral Beam Injection

DIII D Quiescent H-Mode Experiments with Co Plus Counter Neutral Beam Injection Quiescent H-Mode Experiments with Co Plus Counter Neutral Beam Injection by K.H. Burrell for W.P. West, M.E. Fenstermacher, P. Gohil, P.B. Snyder, T.H. Osborne, W.M. Solomon* Lawrence Livermore National

More information

Recent Development Results in Russia of Megawatt Power Gyrotrons for Plasma Fusion Installations

Recent Development Results in Russia of Megawatt Power Gyrotrons for Plasma Fusion Installations EPJ Web of Conferences 32, 04003 (2012) DOI: 10.1051/ epjconf/ 20123204003 C Owned by the authors, published by EDP Sciences, 2012 Recent Development Results in Russia of Megawatt Power Gyrotrons for Plasma

More information

Critical Problems in Plasma Heating/CD in large fusion devices and ITER

Critical Problems in Plasma Heating/CD in large fusion devices and ITER Critical Problems in Plasma Heating/CD in large fusion devices and ITER V.L. Vdovin RRC Kurchatov Institute, Institute of Nuclear Fusion Russia vdov@pike.pike.ru Abstract We identify critical problems

More information

CRITICAL PROBLEMS IN PLASMA HEATING/ CD IN LARGE FUSION DEVICES AND ITER

CRITICAL PROBLEMS IN PLASMA HEATING/ CD IN LARGE FUSION DEVICES AND ITER CRITICAL PROBLEMS IN PLASMA HEATING/ CD IN LARGE FUSION DEVICES AND ITER Vdovin V.L. RRC Kurchatov Institute Nuclear Fusion Institute Moscow, Russia 22nd IAEA Fusion Energy Conference 13-18 October 2008

More information

Physics, Technologies and Status of the Wendelstein 7-X Device

Physics, Technologies and Status of the Wendelstein 7-X Device Physics, Technologies and Status of the Wendelstein 7-X Device F. Wagner on behalf of the W7-X team IPP, BI-Greifswald, EURATOM association Stellarators: toroidal devices with external confinement External

More information

Magnetic Reconnection and Ion Flows During Point Source Helicity Injection on the Pegasus Toroidal Experiment

Magnetic Reconnection and Ion Flows During Point Source Helicity Injection on the Pegasus Toroidal Experiment Magnetic Reconnection and Ion Flows During Point Source Helicity Injection on the Pegasus Toroidal Experiment M.G. Burke, R.J. Fonck, J.L. Barr, K.E. Thome, E.T. Hinson, M.W. Bongard, A.J. Redd, D.J. Schlossberg

More information

Mode-converted Electron Bernstein Waves

Mode-converted Electron Bernstein Waves Mode-converted Electron Bernstein Waves Francesco Volpe currently at Dept of Applied Physics and Applied Mathematics Columbia University, New York Presentation prepared while at Engineering Physics Dept

More information

Whistlers, Helicons, Lower Hybrid Waves: the Physics of RF Wave Absorption for Current Drive Without Cyclotron Resonances

Whistlers, Helicons, Lower Hybrid Waves: the Physics of RF Wave Absorption for Current Drive Without Cyclotron Resonances Whistlers, Helicons, Lower Hybrid Waves: the Physics of RF Wave Absorption for Current Drive Without Cyclotron Resonances R.I. Pinsker General Atomics 100 50 Presented at the 56 th Annual Division of Plasma

More information

Investigation of ion toroidal rotation induced by Lower Hybrid waves in Alcator C-Mod * using integrated numerical codes

Investigation of ion toroidal rotation induced by Lower Hybrid waves in Alcator C-Mod * using integrated numerical codes Investigation of ion toroidal rotation induced by Lower Hybrid waves in Alcator C-Mod * using integrated numerical codes J.P. Lee 1, J.C. Wright 1, P.T. Bonoli 1, R.R. Parker 1, P.J. Catto 1, Y. Podpaly

More information

Workshop on Active control of MHD Stability, Princeton, NJ, 6-8 Nov., RWM control in T2R. Per Brunsell

Workshop on Active control of MHD Stability, Princeton, NJ, 6-8 Nov., RWM control in T2R. Per Brunsell Workshop on Active control of MHD Stability, Princeton, NJ, 6-8 Nov., 2006 RWM control in T2R Per Brunsell P. R. Brunsell 1, J. R. Drake 1, D. Yadikin 1, D. Gregoratto 2, R. Paccagnella 2, Y. Q. Liu 3,

More information

Investigating High Frequency Magnetic Activity During Local Helicity Injection on the PEGASUS Toroidal Experiment

Investigating High Frequency Magnetic Activity During Local Helicity Injection on the PEGASUS Toroidal Experiment Investigating High Frequency Magnetic Activity During Local Helicity Injection on the PEGASUS Toroidal Experiment Nathan J. Richner M.W. Bongard, R.J. Fonck, J.L. Pachicano, J.M. Perry, J.A. Reusch 59

More information

GA A24030 ECE RADIOMETER UPGRADE ON THE DIII D TOKAMAK

GA A24030 ECE RADIOMETER UPGRADE ON THE DIII D TOKAMAK GA A24030 ECE RADIOMETER UPGRADE ON THE DIII D TOKAMAK by M.E. AUSTIN, and J. LOHR AUGUST 2002 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government.

More information

Observation of Toroidal Flow on LHD

Observation of Toroidal Flow on LHD 17 th International Toki conference / 16 th International Stellarator/Heliotron Workshop 27 Observation of Toroidal Flow on LHD M. Yoshinuma, K. Ida, M. Yokoyama, K. Nagaoka, M. Osakabe and the LHD Experimental

More information

Status and Plan for VEST

Status and Plan for VEST Status and Plan for VEST Y.S. Hwang and VEST team Nov. 6, 2015 Dept. of Nuclear Engineering Seoul National University 18 th International Spherical Torus Workshop, Nov. 2-6, 2015, Princeton, NJ, USA Status

More information

An overview of the ITER electron cyclotron H&CD system

An overview of the ITER electron cyclotron H&CD system An overview of the ITER electron cyclotron H&CD system The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation As Published Publisher

More information

Trigger mechanism for the abrupt loss of energetic ions in magnetically confined plasmas

Trigger mechanism for the abrupt loss of energetic ions in magnetically confined plasmas www.nature.com/scientificreports Received: 11 August 2017 Accepted: 30 January 2018 Published: xx xx xxxx OPEN Trigger mechanism for the abrupt loss of energetic ions in magnetically confined plasmas K.

More information

Diagnostic development to measure parallel wavenumber of lower hybrid waves on Alcator C-Mod

Diagnostic development to measure parallel wavenumber of lower hybrid waves on Alcator C-Mod Diagnostic development to measure parallel wavenumber of lower hybrid waves on Alcator C-Mod S. G. Baek, T. Shinya*, G. M. Wallace, S. Shiraiwa, R. R. Parker, Y. Takase*, D. Brunner MIT Plasma Science

More information

Study of Elliptical Polarization Requirement of KSTAR 84-GHz ECH System

Study of Elliptical Polarization Requirement of KSTAR 84-GHz ECH System Journal of the Korean Physical Society, Vol. 49, December 2006, pp. S201 S205 Study of Elliptical Polarization Requirement of KSTAR 84-GHz ECH System Jinhyun Jeong, Youngsoon Bae, Moohyun Cho and Won Namkung

More information

Progress in controlling tearing modes in RFX-mod

Progress in controlling tearing modes in RFX-mod Progress in controlling tearing modes in RFX-mod L. Marrelli A.Alfier,T.Bolzonella, F.Bonomo, L.Frassinetti, M.Gobbin, S.C.Guo, P.Franz, A.Luchetta, G.Manduchi, G.Marchiori, P.Martin, S.Martini, P.Piovesan,

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 Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas Holger Reimerdes With A.M. Garofalo, 1 E.J. Strait, 1 R.J. Buttery, 2 M.S. Chu, 1 Y. In, 3 G.L. Jackson,

More information

Poloidal Transport Asymmetries, Edge Plasma Flows and Toroidal Rotation in Alcator C-Mod

Poloidal Transport Asymmetries, Edge Plasma Flows and Toroidal Rotation in Alcator C-Mod Poloidal Transport Asymmetries, Edge Plasma Flows and Toroidal Rotation in B. LaBombard, J.E. Rice, A.E. Hubbard, J.W. Hughes, M. Greenwald, J. Irby, Y. Lin, B. Lipschultz, E.S. Marmar, K. Marr, C.S. Pitcher,

More information

Performance and Stability Limits at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment

Performance and Stability Limits at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment Performance and Stability Limits at Near-Unity Aspect Ratio in the R. Fonck, S. Diem, G. Garstka, M. Kissick, B. Lewicki, C. Ostrander, P. Probert, M. Reinke, A. Sontag, K. Tritz, E. Unterberg University

More information

High Temporal Resolution Polarimetry on the MST Reversed Field Pinch

High Temporal Resolution Polarimetry on the MST Reversed Field Pinch High Temporal Resolution Polarimetry on the MST Reversed Field Pinch W.X. Ding, S.D. Terry, D.L. Brower Electrical Engineering Department University of California, Los Angeles J.K. Anderson, C.B. Forest,

More information

Field Aligned ICRF Antenna Design for EAST *

Field Aligned ICRF Antenna Design for EAST * Field Aligned ICRF Antenna Design for EAST * S.J. Wukitch 1, Y. Lin 1, C. Qin 2, X. Zhang 2, W. Beck 1, P. Koert 1, and L. Zhou 1 1) MIT Plasma Science and Fusion Center, Cambridge, MA USA. 2) Institute

More information

Experimental Results of Series Gyrotrons for the Stellarator W7-X

Experimental Results of Series Gyrotrons for the Stellarator W7-X Experimental Results of Series Gyrotrons for the Stellarator W7-X FT/P2-24 G. Gantenbein 1, H. Braune 2, G. Dammertz 1, V. Erckmann 2, S. Illy 1, S. Kern 1, W. Kasparek 3, H. P. Laqua 2, C. Lechte 3, F.

More information

Initial Active MHD Spectroscopy Experiments Exciting Stable Alfvén Eigenmodes in Alcator C-Mod

Initial Active MHD Spectroscopy Experiments Exciting Stable Alfvén Eigenmodes in Alcator C-Mod PSFC/JA-03-26 Initial Active MHD Spectroscopy Experiments Exciting Stable Alfvén Eigenmodes in Alcator C-Mod J.A. Snipes, D. Schmittdiel, A. Fasoli*, R.S. Granetz, R.R. Parker 16 December 2003 Plasma Science

More information