Active Control of Neoclassical Tearing Modes toward Stationary High-Beta Plasmas in JT-60U A. Isayama 1), N. Oyama 1), H. Urano 1), T. Suzuki 1), M. Takechi.

Slides:



Advertisements
Similar presentations
H-mode characterization for dominant ECR heating and comparison to dominant NBI or ICR heating F. Sommer PhD thesis advisor: Dr. Jörg Stober Academic advisor:
Advertisements

Rijnhuizen colloquium 18 January 2001 E. Westerhof, FOM-Instituut voor Plasmafysica‘ Rijnhuizen’ Control of Neoclassical Tearing Modes E. Westerhof FOM-Instituut.
Neoclassical Tearing Mode (NTM)
A. Kirk, 21 st IAEA Fusion Energy Conference, Chengdu, China, October 2006 Evolution of the pedestal on MAST and the implications for ELM power loadings.
George Sips ITPA, active control, 14 July Real-time Control ( and development of control systems ) at ASDEX Upgrade George Sips Max-Planck-Institut.
Standard and Advanced Tokamak Operation Scenarios for ITER
6 th ITPA MHD Topical Group Meeting combined with W60 IEA Workshop on Burning Plasmas Session II MHD Stability and Fast Particle Confinement General scope.
Cyclic MHD Instabilities Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Seminar talk at the ‚Advanced Course‘ of EU PhD Network, Garching, September.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
Measurement of magnetic island width by using multi-channel ECE radiometer on HT-7 tokamak Han Xiang( 韩翔 ), Ling Bili( 凌必利 ), Gao Xiang( 高翔 ), Liu Yong(
FOM-Institute for Plasma Physics Rijnhuizen Association Euratom-FOM, Trilateral Euregio Cluster Feedback controlled ECRH power deposition for control of.
Association Euratom-FOM Trilateral Euregio Cluster 1 M.R. de Baar, Workshop Control for Nuclear Fusion, the Netherlands, In the control room:
R Sartori - page 1 20 th IAEA Conference – Vilamoura Scaling Studies of ELMy H-modes global and pedestal confinement at high triangularity in JET R Sartori.
IAEA - FEC2004 // Vilamoura // // EX/4-5 // A. Staebler – 1 – A. Staebler, A.C.C Sips, M. Brambilla, R. Bilato, R. Dux, O. Gruber, J. Hobirk,
TH/3-1Ra Nonperturbative Effects of Energetic Ions on Alfvén Eigenmodes by Y. Todo et al. EX/5-4Rb Configuration Dependence of Energetic Ion Driven Alfven.
Energy loss for grassy ELMs and effects of plasma rotation on the ELM characteristics in JT-60U N. Oyama 1), Y. Sakamoto 1), M. Takechi 1), A. Isayama.
Steady State High  N Discharges and Real-Time Control of Current Profile in JT-60U T. Suzuki 1), A. Isayama 1), Y. Sakamoto 1), S. Ide 1), T. Fujita 1),
Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.
Title – font size to cover width R J Buttery 1, D F Howell 1, R J La Haye 2, T Scoville 2, JET-EFDA contributors* 1 EURATOM/UKAEA Fusion Association, Culham.
H. Urano, H. Takenaga, T. Fujita, Y. Kamada, K. Kamiya, Y. Koide, N. Oyama, M. Yoshida and the JT-60 Team Japan Atomic Energy Agency JT-60U Tokamak: p.
TOTAL Simulation of ITER Plasmas Kozo YAMAZAKI Nagoya Univ., Chikusa-ku, Nagoya , Japan 1.
JT-60U Resistive Wall Mode (RWM) Study on JT-60U Go Matsunaga 松永 剛 Japan Atomic Energy Agency, Naka, Japan JSPS-CAS Core University Program 2008 in ASIPP.
Title – Arial between 80 and 100pt Authors names Arial 50pt, A. N Other 1, 1 Associations Arial 28 pt 2 EURATOM/Culham Fusion Association, Culham Science.
Status of the ASDEX Upgrade Tokamak Programme Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Joint Executive Committee session of IEA-IAs on Pol.
Development and Contribution of RF Heating and Current Drive Systems to Long Pulse, High Performance Experiments in JT-60U Shinichi Moriyama, Masami Seki,
Discussions and Summary for Session 1 ‘Transport and Confinement in Burning Plasmas’ Yukitoshi MIURA JAERI Naka IEA Large Tokamak Workshop (W60) Burning.
MHD Limits to Tokamak Operation and their Control Hartmut Zohm ASDEX Upgrade credits: G. Gantenbein (Stuttgart U), A. Keller, M. Maraschek, A. Mück DIII-D.
High  p experiments in JET and access to Type II/grassy ELMs G Saibene and JET TF S1 and TF S2 contributors Special thanks to to Drs Y Kamada and N Oyama.
Resonant magnetic perturbation effect on the tearing mode dynamics in EXTRAP T2R: experimental results and modeling L. Frassinetti, K.E.J. Olofsson, P.R.
G.Huysmansworkshop : Principles of MHD 21-24/3/2005 MHD in Tokamak Plasmas Guido Huysmans Association Euratom/CEA Cadarache, France with contributions.
Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 8. Heating and current drive Neutral beam heating and current drive,... to be continued.
1 Instabilities in the Long Pulse Discharges on the HT-7 X.Gao and HT-7 Team Institute of Plasma Physics, Chinese Academy of Sciences, P.O.Box 1126, Hefei,
Recent Results of KSTAR
APS DPP 2006 October Adaptive Extremum Seeking Control of ECCD for NTM Stabilization L. Luo 1, J. Woodby 1, E. Schuster 1 F. D. Halpern 2, G.
MHD Suppression with Modulated LHW on HT-7 Superconducting Tokamak* Support by National Natural Science Fund of China No J.S.Mao, J.R.Luo, B.Shen,
Contribution of KIT to LHD Topics from collaboration research on MHD phenomena in LHD S. Masamune, K.Y. Watanabe 1), S. Sakakibara 1), Y. Takemura, KIT.
1 13 th ITPA Transport Physics Group Meeting Naka, 1-3 October 2007 V. Mukhovatov ITER Rotation Issues.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
ITPA Topical Group on MHD, Control, and Disruptions Summary of 5th meeting, Nov. 8-10, 2004 Presented by Ted Strait Workshop on MHD Mode Control Princeton,
ITER STEADY-STATE OPERATIONAL SCENARIOS A.R. Polevoi for ITER IT and HT contributors ITER-SS 1.
JT-60U -1- Access to High  p (advanced inductive) and Reversed Shear (steady state) plasmas in JT-60U S. Ide for the JT-60 Team Japan Atomic Energy Agency.
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
TEC Trilateral Euregio Cluster Institut für PlasmaphysikAssoziation EURATOM-Forschungszentrum Jülich 21st IAEA Fusion Energy Conference, October.
HL-2A Heating & Current Driving by LHW and ECW study on HL-2A Bai Xingyu, HL-2A heating team.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
20th IAEA Fusion Energy Conference, 2004 Naka Fusion Research Establishment, Japan Atomic Energy Research Institute Stationary high confinement plasmas.
FIR-NTMs on ASDEX Upgrade and JET Active Control of (2,1) NTMs on ASDEX Upgrade S. Günter 1, M. Maraschek 1, M. de Baar 2, D.F. Howell 3, E. Strumberger.
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
HT-7 Proposal of the investigation on the m=1 mode oscillations in LHCD Plasmas on HT-7 Exp2005 ASIPP Youwen Sun, Baonian Wan and the MHD Team Institute.
1 E. Kolemen / IAEA / October 2012 Egemen Kolemen 1, A.S. Welander 2, R.J. La Haye 2, N.W. Eidietis 2, D.A. Humphreys 2, J. Lohr 2, V. Noraky 2, B.G. Penaflor.
Off-axis Current Drive and Current Profile Control in JT-60U T. Suzuki, S. Ide, T. Fujita, T. Oikawa, M. Ishikawa, G. Matsunaga, M. Takechi, M. Seki, O.
6 th ITPA MHD Topical Group Meeting combined with W60 IEA Workshop on Burning Plasmas Summary Session II MHD Stability and Fast Particle Confinement chaired.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
O. Sauter “Robust” NTM Control: The AMN-system O. Sauter for the TCV and AUG teams Ecole Polytechnique Fédérale de Lausanne (EPFL) Centre de Recherches.
Decrease of transport coefficients in the plasma core after off-axis ECRH switch-off K.A.Razumova and T-10 team.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Reconnection Process in Sawtooth Crash in the Core of Tokamak Plasmas Hyeon K. Park Ulsan National Institute of Science and Technology, Ulsan, Korea National.
SAWTOOTH AND M=1 MODE BEHAVIOUR IN FTU PELLET ENHANCED DISCHARGES
11th IAEA Technical Meeting on H-mode Physics and Transport Barriers" , September, 2007 Tsukuba International Congress Center "EPOCHAL Tsukuba",
Recent work on the control of MHD instabilities at
Influence of energetic ions on neoclassical tearing modes
T. Morisaki1,3 and the LHD Experiment Group
Stabilization of m/n=1/1 fishbone by ECRH
20th IAEA Fusion Energy Conference,
T. Morisaki1,3 and the LHD Experiment Group
H. Nakano1,3, S. Murakami5, K. Ida1,3, M. Yoshinuma1,3, S. Ohdachi1,3,
Presentation transcript:

Active Control of Neoclassical Tearing Modes toward Stationary High-Beta Plasmas in JT-60U A. Isayama 1), N. Oyama 1), H. Urano 1), T. Suzuki 1), M. Takechi 1), N. Hayashi 1), K. Nagasaki 2), Y. Kamada 1), S. Ide 1), T. Ozeki 1) and the JT-60 team 1) 1) Japan Atomic Energy Agency, Naka, Ibaraki , Japan 2) Institute of Advanced Energy, Kyoto University, Uji, Kyoto , Japan 21st IAEA Fusion Energy Conference, October, 2006, Chengdu, China EX/4-1Ra Control of MHD instabilities by ECCD: ASDEX Upgrade results and implications for ITER EX/4-1Rb H. Zohm 1), G. Gantenbein 2), F. Leuterer 1), A. Manini 1), M. Maraschek 1), Q. Yu 1) and the ASDEX Upgrade Team 1) Max-Planck-Institut für Plasmaphysik, D Garching, Germany, EURATOM Association 2) Forschungszentrum Karlsruhe, IHM, D Karlsruhe, Germany, EURATOM Association

In tokamaks, many kinds MHD instabilities are observed, and they can affect the plasma performance. => Control of MHD instabilities is a key issue to obtain a high-performance plasma MHD instabilities in the core regime Neoclassical Tearing Modes (NTMs) - appear in a high beta plasma - limit the achievable beta at  N <  N ideal Sawtooth Oscillations - have smaller effects on global parameters - sometimes trigger an NTM Active control is important Control tool: Electron Cyclotron Current Drive (ECCD) - highly localized current drive - flexible ECCD location with steerable mirror Introduction

Contents Sawtooth tailoring with ECCD Stabilization of an m/n=3/2 NTM by modulated ECCD and by narrow deposition Control of growth of a 3/2 NTM by central co-ECCD Stabilization of a 2/1 NTM TOPICS code simulation of 2/1 NTM stabilization Summary Sawteeth 3/2 NTM 2/1 NTM This talk: Control of NTM and sawteeth with ECCD in ASDEX-U & JT-60U

Change of sawtooth period by ECCD under otherwise constant conditions wide deposition: ctr-ECCD ineffective (heating effect has opposite sign) narrow deposition: I ECCD /d 2 enhanced w.r.t. heating; ctr-ECCD effective note: due to B t ramp, complete stabilisation could not be studied Sawtooth tailoring with narrow ECCD deposition d/a=0.05d/a=0.02 d: ECCD width I ECCD  exp[-(r/d) 2 ]

The NTM stabilisation efficiency increases with narrow deposition with wide deposition (ITER case), DC ECCD results in partial stabilisation modulation in phase with the island leads to full stabilisation note that this is done with same peak P ECCD, but half average P ECCD NTM stabilisation with narrow deposition Open symbols: partial stabilisation Full symbols: complete stabilisation ~ ECCD current density peaking

Without modulation complete stabilisation was not achieved Scan of the phase of ECCD w.r.t. island O-point shows expected behaviour - full stabilisation with O-point modulation - only partial stabilisation with X-point modulation NTM stabilisation with modulated ECCD O-point modulation X-point modulation Wide deposition (W/(2d)=0.6) ~15kHz modulation

(3,2) NTM stabilisation in improved H-mode at low q 95 = 2.9 After stabilisation, good improved H-mode conditions are recovered NTM stabilisation under ITER relevant conditions H H =1.15  N ~2.6 Narrow Deposition W/(2d)=1.2 (without modulation) Fishbones

Evolution of a 3/2 NTM has been suppressed by central co-ECCD with I ECCD /I p ~0.1 Central co-ECCD can modify j(r) locally and also enhance sawteeth => These changes will also affect the onset & evolution of 3/2 NTM => New scheme for active control of 3/2 NTM  EC =0.1  q=1.5 =0.4 Central co-ECCD before NB I ECCD =130kA(calculation)~0.1I p Low amplitude for 4-unit ECCD even after turn-off of ECCD  N is high for 4-unit ECCD

Change in current profile and/or sawtooth behavior is the candidate for NTM suppression. Sawteeth and a small-amplitude 3/2 NTM can coexist without large confinement degradation by central co-ECCD 7.0s5.7s For 4-unit ECCD, sawtooth amplitude &  inv increase in time Similar temperature profile Electron density is also almost the same  Change in pressure is not likely to be the candidate

m/n=2/1 NTM: Larger confinement degradation or disruption => Active stabilization is essential An m/n=2/1 NTM has been completely stabilized by ECCD at q=2 (  ~0.6) Stabilization for misalignment <~W/2 Destabilization for misalignment ~W “Precise injection is important” After ECCD/ Before ECCD

Further optimization of ECCD location has enabled complete stabilization with J EC /J BS ~0.5 Calculation J EC /J BS : measure of ‘efficiency’ in NTM stabilization Complete stabilization with small J EC /J BS is desirable ‘Marginal island width’ W marg Temporal evolution: 3 phases Similar W marg even for different ECCD location & EC-driven current 2/1 NTM was completely stabilized with 1-unit ECCD (0.6MW, ~5kA)

TOPICS simulation with modified Rutherford equation well reproduces experimental results. Simulation with the same set of coefficients in the modified Rutherford equation Stabilization and destabilization are well reproduced

Extension of ECRH system to multi-frequency, 10 s, 4 MW under way Feedback system for deposition control is being set up: sensors: ECE correlation ECE with same sightline as ECRH mirror on-line q-profile reconstruction actuators: radial shift of plasma position fast (50 ms) steering of poloidal launch angle ASDEX Upgrade enhances its capabilities in this area two-frequency (105/140 GHz) gyrotron (GYCOM) Fast steerable ECRH launcher

R.J. La Haye, R.J. Buttery, N. Hayashi, A. Isayama, M. Maraschek, R. Prater, L. Urso, H. Zohm, EX/P8-12 (Poster on Saturday morning) Another presentation of NTM stabilization Results from cross-machine comparison of NTM stabilization and extrapolation to ITER 2/1 NTM stabilization in ITER  R/d  R (cm) J EC /J BS Multi-machine database of NTM stabilization has been made Prediction analysis on 2/1 NTM stabilization in ITER shows that J EC /J BS =0.9 for perfect alignment J EC /J BS >1 for misaligned ECCD

Summary Active control of NTM and sawteeth with ECCD has been extensively performed in ASDEX-U & JT-60U Narrow ECCD deposition is very effective in - sawtooth tailoring - 3/2 NTM stabilization in an Improved H-mode Effectiveness of modulated ECCD in 3/2 NTM stabilization was demonstrated Appropriate central co-ECCD can suppress the growth of a 3/2 NTM A 2/1 NTM was completely stabilized with J EC /J BS ~0.5 TOPICS simulation well reproduces island evolution in experiments More detailed results of this talk will be presented at the poster session on Saturday morning!

Typical discharge of 2/1 NTM stabilization Mode onset at t~5.8s,  N ~2 (  p ~1.2) Step down of NB power with unidirectional NB at t=7s => Mode rotation from t~8s Unmodulated EC wave injection from t=9.5s. => Complete stabilization at t=10.7s

Evolution of NTM is described by the modified Rutherford equation