IAEA-CN-116 / EX / 7-2
|
|
- Arlene Goodman
- 6 years ago
- Views:
Transcription
1 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 (), A. Mück (), O. Sauter (), H. Zohm (), contributors to the EFDA-JET workprogramme (5) and the ASDEX Upgrade-Team () () Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstr., D Garching, Germany () Institut für Plasmaforschung, Pfaffenwaldring 3, D-7569, Stuttgart, Germany (3) CRPP-EPFL, EURATOM Association, CH-5, Lausanne, Switzerland (4) Euratom Association/UKAEA, Culham Science Centre, Abingdon, United Kingdom (5) see annex of J.Pamela et al., Nucl. Fusion 43 (3) 54 Introduction and motivation Sawtooth tailoring with co / counter ECCD NTM stabilization with co-eccd FIR-NTMs and their triggering with ECCD Summary and future plans th IAEA FEC, Vilamoura, Portugal, -6 November 4
2 Resonant surfaces and MHD modified with ECRH / ECCD #93, 3.99 s deposition q=, (flat or reversed in the centre in adv. scen.): sawteeth, fast particle driven fishbones, (/)-modes sawtooth tailoring, avoidance of NTM trigger q=4/3: (4/3) NTM, ideal (4/3) modes during FIR-NTM artificially trigger / avoid (4/3) FIR-NTM transition q=3/: (3/) NTM stabilisation and suppression of (3/)-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 th IAEA FEC, Vilamoura, Portugal, -6 November 4
3 Sawtooth tailoring with ECRH / ECCD collaboration with T.P.Goodman, O.Sauter (CRPP) normalised sawtooth period τ τo HFS 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 (= 5% co and counter-eccd): - similar behaviour as for co-eccd, but less pronounced - addtional stabilisation when (/) mode is directly hit 7 HFS ctr-eccd LFS normalised sawtooth period τ τo inversion radius complete ST prevention counter-eccd: - stabilisation for on-axis - effect on (/) mode plays an additional role ECR deposition in ρpol PNBI = 5MW, PECCD.4MW th IAEA FEC, Vilamoura, Portugal, -6 November 4 A.Mück, EPS3, St.Petersburg A.Mück, PPCF, to be subm.
4 High power NBI experiments: NTM avoidance at high βn =.8 collaboration with T.P.Goodman, O.Sauter (CRPP) #735 co-eccd #738 counter-eccd NBI *ECR βn (3/)-NTM amplitude ECE time (s) W e6 8e6 4e ev 4 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 higher PNBI = MW to reach NTM-threshold βn.8 fixed by βp feedback NTM avoidance achieved th IAEA FEC, Vilamoura, Portugal, -6 November 4 A.Mück, EPS3, St.Petersburg
5 (3/)-NTM stabilisation with co-eccd at βn =.6 PNI =.5MW * PECCD = MW (3 gyrotr.) MW 5 #93 5 BT complete (3/)-stabilisation T βn, Beta Normalized B[a.u.] (3/) NTM amplitude time (s).4. complete stabilisation at βn =.6 with PECCD = MW and PNBI =.5MW βn / PECCD =.6/MW βn increase with more PNBI not considered even higher βn achievable (re-excitation) th IAEA FEC, Vilamoura, Portugal, -6 November 4
6 Influence of the deposition width on the (3/)-NTM stabilisation I/d [ka/m] 8 I/d [ka/m] 6 4 W min / Wsat W min / Wsat tor angle [deg] narrow depostion: I / d = current density maximal for -5 (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 (modulation experiments will be performed in 5) Jcd [MA/m^] phi = - deg IECCD = 8 ka d =. cm jmax =.7 MA/m phi = -5 deg IECCD = 4 ka d =. cm jmax =.56 MA/m phi = -5 deg IECCD = 9. ka d =.46 cm jmax =.7 MA/m phi = -.5 deg IECCD = 3. ka d =.4 cm jmax =.9 MA/m (Bt = const, ρdep not corrected) ρ p th IAEA FEC, Vilamoura, Portugal, -6 November 4
7 (/)-NTM stabilisation with co-eccd at βn =.3 MW 5 PNI = MW * PECCD =.4MW (4 gyrotr.) 5 #9454 BT complete (/)-stabilisation T - -. (/) NTM amplitude (n=) βn, Beta Normalized time (s).5 B [a.u.] 5-5 V. Locked Mode signal -. stabilisation at βn =.3 [.9] with PECCD =.4MW [.9MW], PNBI = MW [6.5MW] βn / PECCD =.64/MW [./MW] stabilisation of the (/) NTM requires more power (βp,marg, less current drive) current density I/d is the figure of merrit for both NTMs faster unlocking of (/)-NTM injection in the O-point of the locked mode works th IAEA FEC, Vilamoura, Portugal, -6 November 4
8 Nonlinear modelling allows separation of different terms relative island width w/a..5 shift of deposition radius during Bt-scan at 3 cm/s (3,), (6,4) and (,) component togther (,) comp. (3,) comp. time dependent Fokker-Planck code to calculate jeccd(r,t) [G. Giruzzi et al.,nf,39(),7(999)] nonlinear D-MHD (circular cylinder) [Q. Yu and S. Günter, POP,7,3 ()]...5. 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 ((3,)-comp.) and -effect ((,)-comp.) are of similar importance complete stabilisation only due to synergy of both effects th IAEA FEC, Vilamoura, Portugal, -6 November 4
9 FIR-NTMs - a general NTM behaviour for βn >.3 collaboration with D.F.Howell (UKAEA) W W.3 smooth open = ASDEX Upgrade full = JET even n -.. #87 n=3 amplitude. f (khz). 4 (4,3) odd n (3,). FIR 7 5. (,) amplitude (,) β N,onset t (s) common behaviour of FIR-NTM for βn >.3 for JET and ASDEX Upgrade stabilility of required coupled ideal (4/3)-mode (high p, low q infernal mode) ELMs have a similar effect at JET for βn >.9 for low Bt, low q95 presence of q= surface modifies behaviour in improved H-mode th IAEA FEC, Vilamoura, Portugal, -6 November 4
10 Triggering / suppressing of FIR-NTMs with ECCD 5 NBI heating power [MW] (4/3) burst 3 ECRH power [MW] 5 #7955, SXR:C: β N 5 w [a.u.] w [a.u.] ctr-eccd (3,) mode amplitude co-eccd (3,) mode amplitude time (s) f [khz] time [s] triggering of ideal pressure driven (4/3) 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 th IAEA FEC, Vilamoura, Portugal, -6 November 4
11 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) (3) 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 th IAEA FEC, Vilamoura, Portugal, -6 November 4
12 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, NTM avoidance at higher PNBI NTM stabilisation with narrow deposition reduces power requirements (βn/peccd) trigger and suppress FIR-NTM phases physical understanding Outlook: application of feedforward technique: deposition width and modulation experiments with broad deposition, extension towards more general scenarios realtime feedback control with increased ECCD power and control capabilities will be addressed in 5 for stabilisation and avoidance th IAEA FEC, Vilamoura, Portugal, -6 November 4
13 Dependence of the sawtooth frequency on the NBI selesction SXR C3 #667 W/m** 3 variation of tangency radius governs the fast particle distribution from NBI fast particle stabilisation sawtooth period [ms] S3 S7 S4 S8 S S6 S S5 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! th IAEA FEC, Vilamoura, Portugal, -6 November 4
14 Power dependence of the sawtooth behaviour MW.6 MW.4 MW.8 SXR B 3. SXR B co-eccd 3. SXR B 3. co-eccd co-eccd ρpol ~ time (s) ρpol ~ time (s) time (s) #673 #673 #679 W/m** 3 W/m** 3 th IAEA FEC, Vilamoura, Portugal, -6 November 4 W/m** 3 Frequency [Hz] W/m SXR B ECR variation of (/) ampl. with constant sawteeth (/) mode survives role of the (/) mode 5 ρpol~. # signal: B, index: time (s)
15 Stabilisation of neoclassical modes by external current drive in the O-point of the islands P ECRH Experiment ECRH Power (not calibrated) #8 ac: 4kW dc: 8 kw W 5 w /a.. Numerical modelling odd n db dt even n β N n=,3 amplitude n= amplitude time (s) H. Zohm et al. NF 39 (999) 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 is also effective for non-modulated current drive th IAEA FEC, Vilamoura, Portugal, -6 November 4
16 Bt - scan for resonance ECRH (MW) NBI/ (MW) Beta normalized with NTM Beta normalized without NTM n=, Mirnov Signal Shift of EC resonance (cm) Time (s) resonance scanned with 4 kw co - ECCD (+heating) shift of deposition of ECCD: 8 cm shift of mode during scan: cm shot to shot variation of mode location cm resonant intervall 4cm same order as island half width and deposition width th IAEA FEC, Vilamoura, Portugal, -6 November 4 4cm
17 amplitude [a.u.] amplitude [a.u.] amplitude [a.u.] Co / Counter current drive and heating alone ASDEX Upgrade #57, MOD:EvenN, f=khz, smooth=8 co-injection complete stabilisation time [s] ASDEX Upgrade #538, MOD:EvenN, f=khz, smooth=8 counter-injection 45 % reduction time [s] ASDEX Upgrade #345, AUGD:MOD:EvenN, f=khz,smooth=8 pure heating weak mode reduction time [s] comparison between co- and counter-eccd effect(co) = heating + ECCD effect(counter) = heating ECCD heating and ECCD result in a comparable stabilizing and destabilizing heating alone not sufficient to stabilize mode at a given ECRH power th IAEA FEC, Vilamoura, Portugal, -6 November 4 #345 E+7 ECRH Power * Heating Power (NBI) 5E+6 shift of EC resonance Beta Normalised n= amplitude time (s) application of magnetic field ramp ECRH: -5, +5, for co-eccd, counter-eccd, heating W cm
18 FIR-NTMs by nonlinear mode coupling with(m+,n+) modes and (,) mode even n f (khz) #87 n=3 amplitude. (,) amplitude odd n (4,3) (3,) (,) t (s) presence of both (m+/n+) mode and (/) mode required (3,) amplitude (a.u.) f (khz) (4,3) (3,) t (s) # 68.5 f(3,) f(3,) phase locked resonance required th IAEA FEC, Vilamoura, Portugal, -6 November 4 A.Gude, Nucl. Fusion 4 () 833
19 General idea of a feedback loop for NTM stabilisation NTM detection mode numbers ECCD and loop off ECCD and loop on NTM amplitude =, βn - max, WMHD = max,... ECCD localisation mode localisation localisation from calibrated / improved equilibrium mode phase first guess launch angle of ECCD ρntm = ρeccd ECCD modulation launch angle Rplasma, Bt at DIII-D ECCD deposition meas. by ECE TORBEAM calculations for "first guess" for new scenarios ECCD modulation available trigger th IAEA FEC, Vilamoura, Portugal, -6 November 4
20 Newly developed tools for the stabilisation (SENSOR) PNI #93 W.5E+7 E+7 PECCD 5E+6 MOD:EvenN 4 amplitude from FFT tracing RVE:MHD low pass from ECCD trigger time (s) V 8 4 EvenN Trigger detection of odd n ((/)-NTM, but (/) also) and even n ((3/)-NTM) diagnostic upgrade provides realtime n=, n=, n=3 detection detection of localisation of the mode and ECCD via realtime ECE / SXR th IAEA FEC, Vilamoura, Portugal, -6 November 4
21 .3. Detection of mode and ECCD on ECE (SENSOR) 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 Radius [m] 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 5 5 W high time resolution - realtime capabilities - Toroidal Field T Normalised Beta time (s) th IAEA FEC, Vilamoura, Portugal, -6 November A.Keller, EPS3, St. Petersburg
22 The new ECRH system on ASDEX Upgrade (ACTOR) power: 4 MW, provided by 4 gyrotrons pulse length: sec frequency: 5 / 4 GHz as a -f-gyrotron 5 / 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 th IAEA FEC, Vilamoura, Portugal, -6 November 4
2005, M.Maraschek, IPP-Garching. ASDEX Upgrade
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 (),
More informationEXW/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 informationIncreased 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 informationNeoclassical 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 informationPresented 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 informationPRESENT 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 informationGA 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 informationNTM 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 informationSUPPRESSION 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 informationActive 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 informationReal 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 informationECRH 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 informationExperiments 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 informationFeedback 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 informationRF 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 informationICRF 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 informationImproved 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 informationRECENT 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 informationTearing 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 informationNTM 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 informationEX/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 informationOperational 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 informationSystem 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 informationOptimization 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 informationPedestal 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 informationCombined 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 informationRecent 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 informationMax-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 informationTOROIDAL 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 informationEffect 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 informationFaDiS, 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 informationEffect 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 informationSelected 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 informationGA 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 informationRecent 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 informationAdvanced 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 informationAdvanced 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 informationSUMMARY 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 informationElectron 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 informationAbstract. 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 informationDevelopment 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 informationAUTOMATIC 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 information3D 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 informationTask 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 informationThe 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 informationConceptual 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 informationExperimental 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 informationToroidal 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 informationObservation 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 informationLocalization 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 informationNon-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 informationRecent 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 informationExperimental 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 informationAbstract. 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 informationThe 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 informationHigh-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 informationLower 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 informationAn 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 informationFirst 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 informationPLASMA 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 informationObservation 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 informationHelicon 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 informationEffect 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 informationECRF 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 informationNational 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 informationTechnical 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 informationWorkshop 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 informationICRF 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 informationReal-Time Control of ELM and Sawtooth Frequencies: Similarities and Differences
EUROFUSION WPJET1 PR(15)01 M. Lennholm et al. Real-Time Control of ELM and Sawtooth Frequencies: Similarities and Differences Preprint of Paper to be submitted for publication in Nuclear Fusion This work
More informationInvestigating 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 informationINITIAL 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 informationInitial 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 informationLocked-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 informationMode-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 informationDIII 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 informationHigh-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 informationRF 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 informationC-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 informationTrigger 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 informationHelicon 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 informationHeating 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 informationLong Pulse EBW Start-up Experiments in MAST
Long Pulse EBW Start-up Experiments in MAST V.F. Shevchenko 1, a, T. Bigelow 2, J.B. Caughman 2, S. Diem 2, J. Mailloux 1, M.R. O Brien 1, M. Peng 2, A.N. Saveliev 3, Y. Takase 4, H. Tanaka 5, G. Taylor
More informationObservation 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 informationCRITICAL 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 informationToroidal 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 informationStatus 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 informationMagnetic 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 informationSensitivity 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 informationParticle Simulation of Lower Hybrid Waves in Tokamak Plasmas
Particle Simulation of Lower Hybrid Waves in Tokamak Plasmas J. Bao 1, 2, Z. Lin 2, A. Kuley 2, Z. X. Wang 2 and Z. X. Lu 3, 4 1 Fusion Simulation Center and State Key Laboratory of Nuclear Physics and
More informationFeedback 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 informationMicrowave Experiments on Prairie View Rotamak
Microwave Experiments on Prairie View Rotamak R. J. Zhou,, M. Xu, and Tian-Sen Huang ) Prairie View A&M University, Prairie View, Texas 776, USA ) Institute of Plasma Physics, Chinese Academy of Sciences,
More informationInterdependence of Magnetic Islands, Halo Current and Runaway Electrons in T-10 Tokamak
IAEA-CN-77/EXP2/02 Interdependence of Magnetic Islands, Halo Current and Runaway Electrons in T-10 Tokamak N.V. Ivanov, A.M. Kakurin, V.A. Kochin, P.E. Kovrov, I.I. Orlovski, Yu.D.Pavlov, V.V. Volkov Nuclear
More informationCommissioning of inline ECE system within waveguide based ECRH transmission systems on ASDEX upgrade
Downloaded from orbit.dtu.dk on: Dec 20, 2017 Commissioning of inline ECE system within waveguide based ECRH transmission systems on ASDEX upgrade Bongers, W. A.; Kasparek, W.; Doelman, N.; van den Braber,
More informationObservation of Short Time-Scale Spectral Emissions at Millimetre Wavelengths with the New CTS Diagnostic on the FTU Tokamak
Bruschi DOI:10.1088/1741-4326/aa6ce1 EX/P8-23 Observation of Short Time-Scale Spectral Emissions at Millimetre Wavelengths with the New CTS Diagnostic on the FTU Tokamak A. Bruschi 1, E. Alessi 1, W. Bin
More informationExperimental 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 informationObservation of Cryogenic Hydrogen Pellet Ablation with a fast-frame camera system in the TJ-II stellarator
EUROFUSION WPS1-PR(16) 15363 N Panadero et al. Observation of Cryogenic Hydrogen Pellet Ablation with a fast-frame camera system in the TJ-II stellarator Preprint of Paper to be submitted for publication
More informationReflectometry for density and fluctuation measurement on EAST
Reflectometry for density and fluctuation measurement on EAST *, Shoubiao Zhang, Fei Wen, Hao Qu, Yumin Wang, Xiang Han, Defeng Kong, Xiang Gao and EAST contributor Institute of Plasma Physics, Chinese
More informationProfile Scan Studies on the Levitated Dipole Experiment
Profile Scan Studies on the Levitated Dipole Experiment Columbia University A.K. Hansen, D.T. Garnier, M.E. Mauel, E.E. Ortiz Columbia University J. Kesner, A.C. Boxer, J.E. Ellsworth, I. Karim, S. Mahar,
More informationGA 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 informationAbstract. PEGASUS Toroidal Experiment University of Wisconsin-Madison
Abstract Extensive new capabilities have been installed on the Pegasus ST facility. The laboratory has been completely reconfigured to separate all power systems from the main hall. Data acquisition, control,
More information