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.

Slides:



Advertisements
Similar presentations
EXTENDED MHD SIMULATIONS: VISION AND STATUS D. D. Schnack and the NIMROD and M3D Teams Center for Extended Magnetohydrodynamic Modeling PSACI/SciDAC.
Advertisements

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:
Active Control of MHD Stability, Austin, 3-5 November 2003J.A. Hoekzema, FZ-Juelich / IPP Association EURATOM-FOM FOM-Instituut voor Plasmafysica “Rijnhuizen”
George Sips ITPA, active control, 14 July Real-time Control ( and development of control systems ) at ASDEX Upgrade George Sips Max-Planck-Institut.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
1 J-W. Ahn a H.S. Han b, H.S. Kim c, J.S. Ko b, J.H. Lee d, J.G. Bak b, C.S. Chang e, D.L. Hillis a, Y.M. Jeon b, J.G. Kwak b, J.H. Lee b, Y. S. Na c,
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Real time operation of MAST TS diagnostic S. Shibaev, G. Naylor, R. Scannell,
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.
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,
Energy Department The MHD Control System for the FTU Tokamak Gabriele D’Antona, Sante Cirant, Mohsen Davoudi RTC 2010.
XP810 and 801 report, Feb 08 slide 1 Buttery, Gerhardt, La Haye, Sabbagh June 2008 reporting meeting – XP810 and 801 experiment: 801: Marginal island width.
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),
18 August 09Mark Rayner – Momentum measurement by The TOFs1 Momentum measurement by the TOFs A correction to an O(4 MeV/c) bias on the current muon momentum.
12/01/2004 E.Lazzaro Plasmi04, Arcetri Real-time tracking and feedback control strategies for rotating magnetic islands E. Lazzaro with the contribution.
By C. P. Moeller General Atomics, San Diego, California , USA RF Launchers That Survive Presented at the Renew theme III workshop at UCLA, March.
SLHC-PP – WP7 Critical Components for Injector Upgrade Plasma Generator – CERN, DESY, STFC-RAL Linac4 2MHz RF source Thermal Modeling Gas Measurement and.
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
1 Electron Bernstein Wave Research and Plans Gary Taylor Presentation to the 16th NSTX Program Advisory Committee September 9, 2004.
NSTX The Resistive Wall Mode and Beta Limits in NSTX S. A. Sabbagh 1, J. Bialek 1, R. E. Bell 2, A. H. Glasser 3, B. LeBlanc 2, J.E. Menard 2, F. Paoletti.
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.
SIMULATION OF A HIGH-  DISRUPTION IN DIII-D SHOT #87009 S. E. Kruger and D. D. Schnack Science Applications International Corp. San Diego, CA USA.
Overview of MHD and extended MHD simulations of fusion plasmas Guo-Yong Fu Princeton Plasma Physics Laboratory Princeton, New Jersey, USA Workshop on ITER.
TH/7-2 Radial Localization of Alfven Eigenmodes and Zonal Field Generation Z. Lin University of California, Irvine Fusion Simulation Center, Peking University.
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.
Development and Contribution of RF Heating and Current Drive Systems to Long Pulse, High Performance Experiments in JT-60U Shinichi Moriyama, Masami Seki,
Rotation effects in MGI rapid shutdown simulations V.A. Izzo, P.B. Parks, D. Shiraki, N. Eidietis, E. Hollmann, N. Commaux TSD Workshop 2015 Princeton,
1 Humphreys/55 th APS-DPP/October 2012 D.A. Humphreys 1, G.L. Jackson 1, R. Hawryluk 2, E. Kolemen 2, D. Moreau 3, A. Pironti 4, G. Raupp 5, O. Sauter.
Clustered Surface RF Production Scheme Chris Adolphsen Chris Nantista SLAC.
Current Drive for FIRE AT-Mode T.K. Mau University of California, San Diego Workshop on Physics Issues for FIRE May 1-3, 2000 Princeton Plasma Physics.
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.
Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 8. Heating and current drive Neutral beam heating and current drive,... to be continued.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
D. Moreau, ITPA-IOS Meeting, Kyoto, October 18-21, 2011 LEHIGH U N I V E R S I T Y First Integrated Magnetic and Kinetic Control for AT Scenarios on DIII-D.
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.
Advances In High Harmonic Fast Wave Heating of NSTX H-mode Plasmas P. M. Ryan, J-W Ahn, G. Chen, D. L. Green, E. F. Jaeger, R. Maingi, J. B. Wilgen - Oak.
FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.
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,
Progress on NSTX towards steady state at low aspect ratio D. A. Gates, Princeton Plasma Physics Laboratory on behalf of the NSTX Research Team Supported.
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*
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,
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.
QAS Design of the DEMO Reactor
David Hutchcroft 1 VELO software. Lite clusters in Kalman fit 2 The VELO clusters are available both as a lite and “full” version Two consecutive blocks.
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Taming The Physics For Commercial Fusion Power Plants ARIES Team Meeting.
MHD Issues and Control in FIRE C. Kessel Princeton Plasma Physics Laboratory Workshop on Active Control of MHD Stability Austin, TX 11/3-5/2003.
20th IAEA Fusion Energy Conference, 2004 Naka Fusion Research Establishment, Japan Atomic Energy Research Institute Stationary high confinement plasmas.
Discussion Slides S.E. Kruger, J.D. Callen, J. Carlson, C.C. Hegna, E.D. Held, T. Jenkins, J. Ramos, D.D. Schnack, C.R. Sovinec, D.A. Spong ORNL SWIM Meet.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
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.
47th Annual Meeting of the Division of Plasma Physics, October 24-28, 2005, Denver, Colorado ECE spectrum of HSX plasma at 0.5 T K.M.Likin, H.J.Lu, D.T.Anderson,
1 NSTX EXPERIMENTAL PROPOSAL - OP-XP-712 Title: HHFW Power Balance Optimization at High B Field J. Hosea, R. Bell, S. Bernabei, L. Delgado-Aparicio, S.
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.
3/2 NTMs, XP 834, X/X/20081 XP 834: Threshold and Small Island Physics of the 3/2 NTM S.P. Gerhardt, D. Gates Helpful discussions with E. Fredrickson,
APS DPP 2006 October Dependence of NTM Stabilization on Location of Current Drive Relative to Island J. Woodby 1 L. Luo 1, E. Schuster 1 F. D.
Effects of Symmetry-Breaking on Plasma Formation and Stored Energy in HSX Presented by D.T. Anderson for the HSX Team University of Wisconsin-Madison 2001.
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.
Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod S. D. Scott Princeton Plasma Physics Laboratory In collaboration with R. Granetz, D. Beals, C.
1 V.A. Soukhanovskii/IAEA-FEC/Oct Developing Physics Basis for the Radiative Snowflake Divertor at DIII-D by V.A. Soukhanovskii 1, with S.L. Allen.
TH/7-1Multi-phase Simulation of Alfvén Eigenmodes and Fast Ion Distribution Flattening in DIII-D Experiment Y. Todo (NIFS, SOKENDAI) M. A. Van Zeeland.
Hard X-rays from Superthermal Electrons in the HSX Stellarator Preliminary Examination for Ali E. Abdou Student at the Department of Engineering Physics.
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.
RF manipulations in SIS 18 and SIS 100 O. Chorniy.
OVERVIEW OF THE DIII–D PROGRAM AND CONSTRUCTION PLANS
20th IAEA Fusion Energy Conference,
Presentation transcript:

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 2, R. Prater 2, and F. Turco 3 1) Princeton Plasma Physics Laboratory, Princeton, NJ, USA 2) General Atomics, San Diego, CA, USA 3) Columbia University, 116 th St and Broadway, New York, NY 10027, USA Presented at IAEA Meeting, October, 2012 State-of-the-Art Neoclassical Tearing Mode Control in DIII-D Using Real-time Steerable Electron Cyclotron Current Drive Launchers Catch & Subdue

2 E. Kolemen / IAEA / October 2012 New fully automatic NTM control system at DIII-D integrates all the Real-Time (RT) components of mode detection, location, suppression. New control strategy “ Catch and Subdue ” can reduce the EC power use; lead to higher Q and reduce disruption risk in ITER Fully Automatic NTM Control Using Real-Time Mirror Steering Can Suppress the 2/1 Mode

3 E. Kolemen / IAEA / October 2012 In ITER, without ECCD, 2/1 Islands Can Grow and Cause Disruptions Loss of H-mode and disruption is expected after locking Need robust and efficient NTM control strategies DIII-D experiment ITER Simulation La Haye IAEA 2008

4 E. Kolemen / IAEA / October 2012 Accurate Alignment of ECCD to Resonant Surface Suppresses Neoclassical Tearing Mode Steerable Launcher Mirror 5 Gyrotrons (~2.8 MW injected) Align the Electron Cyclotron Current Drive deposition with the Neoclassical Tearing Mode (NTM) island for suppression Mirrors steered to move the beam vertically along the EC resonance for best alignment

5 E. Kolemen / IAEA / October 2012 Accurate Alignment of ECCD to Resonant Surface Suppresses Neoclassical Tearing Mode Align the Electron Cyclotron Current Drive deposition with the Neoclassical Tearing Mode (NTM) island for suppression Mirrors steered to move the beam vertically along the EC resonance for best alignment Steerable Launcher Mirror 5 Gyrotrons (~2.8 MW injected)

6 E. Kolemen / IAEA / October 2012 Diagnostics  Detect NTM / Find Location Mirror Control System Mirror Control System Plasma Control System (PCS) Plasma Control System (PCS) Gyrotrons Control System Gyrotrons Control System rf beam EC Launcher DIII-D NTM Control System Overview

7 E. Kolemen / IAEA / October 2012 Real time MSE Equilibria Enable Precise Tracking of Resonant Surface Real time MSE tracks q=3/2 or 2 Calculate intersection point of the q surface with 2f ce Move the mirrors to align the ECCD with NTM Tracking performance with minimal overshoot and <1 cm error. Calibration: – ECCD deposition: with 100 Hz ECCD modulation – NTM location: with ECE based calculation & Sweeps across NTM – Mapping of angle in mirror to position in plasma: Ray tracing  Δz

8 E. Kolemen / IAEA / October 2012 Application to the 3/2 NTM: – Head room to develop the technique

9 E. Kolemen / IAEA / October 2012 NTM Control Methods: Successful 3/2 NTM Suppression After Mode Saturation

10 E. Kolemen / IAEA / October 2012 NTM Control Methods: Preemptive NTM Suppression Achieved Without ECCD, 3/2 NTM develops NTM Preemption with ECCD

11 E. Kolemen / IAEA / October 2012 Minimize EC Use for Higher Q Operation ITER strategies: – Preemptive suppression: uses continuous power, decreases Q – Suppression after saturation: requires large power and long time, risking disruptions – Preferable to intercept mode while still small Q P EC (MW) Q=10 operating point Pre-emptive stabilization with 7 or 20MW 3/2 NTM 2/1 NTM Modes drop performance [Zohm, IAEA 2006] Pre-emptive suppression

12 E. Kolemen / IAEA / October 2012 New "Catch and Subdue" Technique is More Efficient Detect Example of 3/2 Catch&Subdue ms Continuous q-surface Following – Constantly calculate q-surface – Track w/ mirrors; be ready to suppress Detect that island is forming (2/1 or 3/2) – Real-time Fourier analysis of Mirnov diagnostics Turn Gyrotrons ON when the mode is detected Result: Catch the island before it saturates – Island saturation for 2/1 mode ~ ms, 3/2 mode ~200ms

13 E. Kolemen / IAEA / October 2012 Catch and Subdue Technique Enables Much Faster Suppression and Reduced ECCD Power : No ECCD (Beam drops after 5 sec) : Catch and Subdue (Many more examples) Control Start Results: – Less power needed : Suppression with 3 gyrotrons instead of 5 for fully saturated modes – Faster suppression (~140 ms after the gyrotrons turn on) – Avoids continuous power deposition of the preemptive approach

14 E. Kolemen / IAEA / October 2012 Catch and Subdue Even Works Well Starting from a Misalignment of ECCD and q Surface Experiment: Intentional mirror misalignment ~4 cm Result: System rapidly corrects deposition location Fast suppression: complete suppression takes ~40 ms longer than aligned case

15 E. Kolemen / IAEA / October 2012 Saturated Mode Suppression of 3/2 NTM Requires Good Alignment & J eccd >J boot Color=Mode amplitude (Gauss) J eccd ~J boot EC Power (MW) No mode 1.Power: Peak ECCD (J eccd ) > local bootstrap current density (J boot )  To replace the missing current in the island. 2.Alignment: ECCD aligned with the 3/2 island within the half width of the ECCD profile Alignment: (ρ 3/2 -ρ eccd )/FWHM eccd Contour plot of Mode Amplitude Saturated Suppression

16 E. Kolemen / IAEA / October 2012 Catch and Subdue Needs Less Power Color=Mode amplitude (Gauss) J eccd ~J boot EC Power (MW) No mode Catch and Subdue needs less power compared to saturated mode suppression. C&S+Saturated Suppression Alignment: (ρ 3/2 -ρ eccd )/FWHM eccd Contour plot of Mode Amplitude

17 E. Kolemen / IAEA / October 2012 Preemptive ECCD Reduces Power Requirement for 3/2 Suppression by Over 50% J eccd ~J boot Preemptiv e EC Power (MW) No mode Preemption reduces the power threshold. Color=Mode amplitude (Gauss) Alignment: (ρ 3/2 -ρ eccd )/FWHM eccd Contour plot of Mode Amplitude

18 E. Kolemen / IAEA / October 2012 Early Mode Detection is Key for Rapid NTM Suppression Below the critical amplitude small island effect takes over which enable fast suppression Above the critical amplitude the mode saturates and suppression takes more than a second or becomes unachievable *All shots with same β N and ECCD is actively aligned with a power of 1.5±0.2 MW at the island location. Critical amplitude (knee) 2 late “catch” shots 3 early “catch” shots

19 E. Kolemen / IAEA / October 2012 Application to the 2/1 NTM: – Most challenging and important case

20 E. Kolemen / IAEA / October 2012 Successful 2/1 NTM Catch and Subdue Demonstrated Peak mode amplitude is reduced; without ECCD, mode reaches ~40 G and locks with loss of H-mode The mode is brought to full suppression Time [ms]

21 E. Kolemen / IAEA / October 2012 No mode EC Power (MW) J eccd ~J boot at q=2 Alignment: (ρ 2/1 -ρ eccd )/FWHM eccd Catch and Subdue Suppression Catch & Subdue suppression of 2/1 pushes the limit of the available EC power 2/1 Mode Suppression Requires Good Alignment & J eccd >J boot Color=Mode amplitude (Gauss) Contour plot of Mode Amplitude

22 E. Kolemen / IAEA / October 2012 EC Power (MW) J eccd ~J boot at q=2 Alignment: (ρ 2/1 -ρ eccd )/FWHM eccd Preemption Catch and Subdue + Preemption No mode Preemption reduces the power threshold. Preemptive ECCD Reduces Power Requirement for 2/1 Suppression by 40% Color=Mode amplitude (Gauss) Contour plot of Mode Amplitude

23 E. Kolemen / IAEA / October 2012 Faster Suppression Needs Early Mode Detection for “Catch and Subdue” Islands caught bigger than the critical amplitude takes much longer to suppress Noise from sawteeth and ELMs are hindrance for small island detection – Also important for ITER Detection below the critical amplitude would reduce the energy even even lower Critical Amplitude (knee) #150783, #150792

24 E. Kolemen / IAEA / October 2012 Integration of NTM Control Elements Has Demonstrated the Ability to Efficiently Control NTMs in ITER Advanced integrated control: – Mode detection with Fourier analysis of the Mirnov diagnostics – Real-time high accuracy equilibrium reconstruction with MSE – Fast EC steerable mirrors – Fully automatic control algorithm “catch and subdue” that fuses all the ingredients. Provides an efficient approach for ITER – Reduces power requirements for NTM control – Reduces time to suppress modes – Decreases adverse effects on confinement & disruption – Enables higher Q in ITER Catch & Subdue