Recent Results of KSTAR

Slides:



Advertisements
Similar presentations
Stability, Transport, and Conrol for the discussion Y. Miura IEA/LT Workshop (W59) combined with DOE/JAERI Technical Planning of Tokamak Experiments (FP1-2)
Advertisements

ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.
Thermal Load Specifications from ITER C. Kessel ARIES Project Meeting, May 19, 2010 UCSD.
George Sips ITPA, active control, 14 July Real-time Control ( and development of control systems ) at ASDEX Upgrade George Sips Max-Planck-Institut.
ELM Filament Propogation Measurements on MAST A. Kirk a, N. B. Ayed b, B. Dudson c, R. Scannel d (a) UKAEA Culham, (b) University of York, (c) University.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
1 Recent Experimental Results on HL-2A HL-2A Team presented by X.T. Ding Southwestern Institute of Physics, Chengdu, China In collaboration with USTC,
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,
HL-2A Southwestern Institute of Physics 1/15 Experimental Studies of ELMy H-mode on HL-2A Tokamak Y. Huang J.Q.Dong, L.W.Yan, X.T.Ding X.R.Duan, HL-2A.
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.
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.
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.
M.E. Fenstermacher - Summary of Progress and Outlook for Work Plan in PEP ITPA WG on RMP ELM Control 4/23/09 11:15 PM 1 PEP ITPA Working Group on RMP ELM.
Parallel and Poloidal Sheared Flows close to Instability Threshold in the TJ-II Stellarator M. A. Pedrosa, C. Hidalgo, B. Gonçalves*, E. Ascasibar, T.
1 ST workshop 2005 Numerical modeling and experimental study of ICR heating in the spherical tokamak Globus-M O.N.Shcherbinin, F.V.Chernyshev, V.V.Dyachenko,
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.
10th ITPA TP Meeting - 24 April A. Scarabosio 1 Spontaneous stationary toroidal rotation in the TCV tokamak A. Scarabosio, A. Bortolon, B. P. Duval,
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
Edge Localized Modes propagation and fluctuations in the JET SOL region presented by Bruno Gonçalves EURATOM/IST, Portugal.
ASIPP Overview of EAST H-mode Plasma Liang Wang*, J. Li, B.N. Wan, H.Y. Guo, Y. Liang, G.S. Xu, L.Q. Hu for EAST Team & Collaborators Institute of Plasma.
L. Chen US TTF meeting, 2014 April 22-25, San Antonio, Texas 1 Study on Power Threshold of the L-I-H Transition on the EAST Superconducting Tokamak L.
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
Mid-Run Assessment - ISD S. Kaye, D. Gates 10 May 2006.
Overview of the KSTAR commissioning M. Kwon 3 June, 2008.
NSTX-U NSTX-U PAC-31 Response to Questions – Day 1 Summary of Answers Q: Maximum pulse length at 1MA, 0.75T, 1 st year parameters? –A1: Full 5 seconds.
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
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.
Toroidal rotation in ECRH L-mode, I-phase and H-mode on HL-2A tokamak A.P. Sun, J.Q. Dong, X.Y. Han, C.H. Liu, J.Y. Cao, M. Huang, Y.G. Li, X. L. Huang.
ARIES-AT Physics Overview presented by S.C. Jardin with input from C. Kessel, T. K. Mau, R. Miller, and the ARIES team US/Japan Workshop on Fusion Power.
EAST Data processing of divertor probes on EAST Jun Wang, Jiafeng Chang, Guosheng Xu, Wei Zhang, Tingfeng Ming, Siye Ding Institute of Plasma Physics,
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
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,
Fusion Fire Powers the Sun Can we make Fusion Fire on earth? National FIRE Collaboration AES, ANL, Boeing, Columbia U., CTD, GA, GIT, LLNL, INEEL, MIT,
1 Confinement Studies on TJ-II Stellarator with OH Induced Current F. Castejón, D. López-Bruna, T. Estrada, J. Romero and E. Ascasíbar Laboratorio Nacional.
ASIPP Long pulse and high power LHCD plasmas on HT-7 Xu Qiang.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
Current holes at ASDEX Upgrade Presented by O. Gruber for D. Merkl, J. Hobirk, P.J. McCarthy, E. Strumberger, ASDEX Upgrade Team - hardware upgrades for.
Measurement of toroidal rotation velocity profiles in KSTAR S. G. Lee, Y. J. Shi, J. W. Yoo, J. Seol, J. G. Bak, Y. U. Nam, Y. S. Kim, M. Bitter, K. Hill.
ASIPP HT-7 The effect of alleviating the heat load of the first wall by impurity injection The effect of alleviating the heat load of the first wall by.
HL-2A Jiaqi Dong Southwestern Institute of Physics & Institute for Fusion Theory and Simulation, ZJU International West Lake Workshop on Fusion Theory.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
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)
HL-2A Heating & Current Driving by LHW and ECW study on HL-2A Bai Xingyu, HL-2A heating team.
Work with TSC Yong Guo. Introduction Non-inductive current for NSTX TSC model for EAST Simulation for EAST experiment Voltage second consumption for different.
N. Nishino, T. Mizuuchi a, S.Kobayashi a, S.Yamamoto a, H.Okada a, K.Nagasaki a, T.Minami a, F.Sano a ISHW /10/13 PPPL Peripheral plasma measurement.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
1 L.W. Yan, Overview on HL-2A, 23rd IAEA FEC, Oct. 2010, Daejeon, Republic of Korea HL-2A 2 nd Asia-Pacific Transport Working Group Meeting ELM mitigation.
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,
MCZ Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2,
20th IAEA Fusion Energy Conference, 2004 Naka Fusion Research Establishment, Japan Atomic Energy Research Institute Stationary high confinement plasmas.
Enhanced D  H-mode on Alcator C-Mod presented by J A Snipes with major contributions from M Greenwald, A E Hubbard, D Mossessian, and the Alcator C-Mod.
LI et al. 1 G.Q. Li 1, X.Z. Gong 1, A.M. Garofalo 2, L.L. Lao 2, O. Meneghini 2, P.B. Snyder 2, Q.L. Ren 1, S.Y. Ding 1, W.F. Guo 1, J.P. Qian 1, B.N.
Page 1 Alberto Loarte- NSTX Research Forum st - 3 rd December 2009  ELM control by RMP is foreseen in ITER to suppress or reduce size of ELM energy.
The International Workshop on Thin Films. Padova 9-12 Oct of slides Present Status of the World- wide Fusion Programme and possible applications.
Radiation divertor experiments in the HL-2A tokamak L.W. Yan, W.Y. Hong, M.X. Wang, J. Cheng, J. Qian, Y.D. Pan, Y. Zhou, W. Li, K.J. Zhao, Z. Cao, Q.W.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
1 Young-Ju Lee Vacuum & Cryogenic Engineering Team National Fusion Research Institute Young-Ju Lee Vacuum & Cryogenic Engineering Team National Fusion.
Si-Woo Yoon on behalf of KSTAR Team and collaborators National Fusion Research Institute (NFRI), Daejeon, Korea Oct th Fusion Energy Conference,
Reconnection Process in Sawtooth Crash in the Core of Tokamak Plasmas Hyeon K. Park Ulsan National Institute of Science and Technology, Ulsan, Korea National.
ELM Control in Application of Non-Axisymmetric Magnetic Perturbations
Andrew Kirk on behalf of
L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.
Stabilization of m/n=1/1 fishbone by ECRH
Max-Planck Institut für Plasmaphysik Garching
20th IAEA Fusion Energy Conference,
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

Recent Results of KSTAR H-modes, ELM Mitigations And TM stabilisation Yong-Su Na on behalf of the KSTAR Team

Contents Short introduction to KSTAR H-modes L-H transition power threshold Characteristics of H-mode discharges Effect of ECRH on rotation Control of Edge Localized Modes Effect of resonant magnetic perturbation Direct pedestal heating by ECRH ELM mitigation by SMBI ELM pacemaking by Vertical jog Control of Tearing Modes 2

KSTAR Mission and Achievements KSTAR Parameters PARAMETERS Designed Achieved To achieve the superconducting tokamak construction and operation experiences, and To develop high performance steady-state operation physics and technologies that are essential for ITER and fusion reactor development Major radius, R0 Minor radius, a Elongation,  Triangularity,  Plasma volume Bootstrap Current, fbs PFC Materials Plasma shape Plasma current, IP Toroidal field, B0 Pulse length N Plasma fuel Superconductor Auxiliary heating /CD Cryogenic 1.8 m 0.5 m 2.0 0.8 17.8 m3 > 0.7 C, CFC (W) DN, SN 2.0 MA 3.5 T 300 s 5.0 H, D Nb3Sn, NbTi ~ 28 MW 9 kW @4.5K 1.8 m 0.5 m 2.0 0.8 17.8 m3 - C DN 1.0 MA 3.6 T 10 s > 1.5 H, D, He Nb3Sn, NbTi 2.0 MW 5 kW @4.5 K Black : achieved Red : by 2011 3

Cryogenic helium supply KSTAR Device for 2011 Campaign PFC Baking & Cooling 200 C NBI-1 100 keV 1.5 MW, 10 s ECH 170 GHz 0.7 MW, cw vacuum pumping ECH 84 GHz / 110 GHz 0.3 MW, 2 s ICRF 0.5MW, 1s Cryogenic helium supply 4.5 K, 600 g/s

Contents Short introduction to KSTAR H-modes L-H transition power threshold Characteristics of H-mode discharges Effect of ECRH on rotation Control of Edge Localized Modes Effect of resonant magnetic perturbation Direct pedestal heating by ECRH ELM mitigation by SMBI ELM pacemaking by Vertical jog Control of Tearing Modes 5

Typical H-mode in KSTAR (2010) #4333 H-mode ELMs Da ~30 shots achieved in 5 days BT = 2 T, Ip ~ 0.6 MA, ne ~ 2e19 m-3 PNBI ~ 1.3 MW (80 keV, co-NBI) PECH ~ 0.25 MW (cntr-injection to Ip) POH ~ 0.2 MW Double null, κ ~ 1.8, R ~ 1.8 m, a ~ 0.5 m Boronization with carborane Pthres ~1.1 MW (ITER physics basis, 1999) sharp increase of edge ECE ~80% increase of βp

Roll-over of H-mode threshold power at low density 𝐏 𝐭𝐡𝐫, 𝐬𝐜𝐚𝐥𝐢𝐧𝐠 =𝟎.𝟎𝟒𝟖𝟖±𝟎.𝟎𝟎𝟐𝟖 𝐧 𝐞𝟐𝟎 𝟎.𝟕𝟏𝟕±𝟎.𝟎𝟑𝟓 𝐁 𝐓 𝟎.𝟖𝟎𝟑±𝟎.𝟎𝟑𝟐 𝐒 𝟎.𝟗𝟒𝟏±𝟎.𝟎𝟏𝟗 Progress in ITER Physics Basis (2007)

Energy Confinement Time is in Line with Multi-Machine Database for L- and H-mode E estimated using measured stored energy and ASTRA simulation with some assumptions Assuming 20% (due to low density regime) fast ion fraction in the stored energy, the experimental E was estimated L-mode: E= ~86ms, HL96=1.3 H-mode: E=~130ms, HH98=1.1

Extended Operation Boundary to high βN

Structure of pedestal from CES measurements Pedestal width is larger for VT Width of Ti ~2.5 cm Width of VT ~3.5 cm

ECH effect on toroidal rotation in H-mode (by XICS measurements) Core Ti drop

Rotation drop is larger for the central region CES measurements

Smaller counter torque with off-axis ECH Scan of ECH deposition layer Smaller drop of Ti

Contents Short introduction to KSTAR H-modes L-H transition power threshold Characteristics of H-mode discharges Effect of ECRH on rotation Control of Edge Localized Modes Effect of resonant magnetic perturbation Direct pedestal heating by ECRH ELM mitigation by SMBI ELM pacemaking by Vertical jog Control of Tearing Modes 1414

2D ECEI Observation: A Single Large ELM Crash Event Consisted of A Series of Multiple Filament Bursts A single large ELM crash was composed of a series of multiple filament bursts Similar observations on ion saturation currents measured from divertor probes  Time [sec] Inner Divertor (EP 42) Outer Divertor (EP 54) KSTAR #4362 Courtesy by G.S. Yun (Postech) and J.G. Bak(NFRI) PRL 2011

Suppression of ELMs with n=1 Resonant magnetic perturbations Top-RMP Mid-RMP Bot-RMP BT=2.0T PNBI=1.4MW 90 phasing RMP strongly mitigated or suppressed ELMs In JET, ELM mitigated by n=1 (Y.Liang, PRL, 2007) Two distinctive phases observed ELM excitation phase ELM suppression phase Density (~10%) pumping out initially. Then, increasing when ELM suppressed Stored energy drop by ~8% initially. Then slightly increased or sustained when ELM suppressed Rotation decreased (~10%) initially. Then sustained when ELM suppressed Te/Ti changes were relatively small

Strong locking observed instead of ELM-Suppression at relatively high edge Te 17

Direct ECH in the pedestal region Optimal edge heating at BT0 = 2.3 T

ECH near pedestal increases fELM Shot 6313 At relatively low ν* fELM before ECH ~20~30 Hz fELM during ECH ~40 Hz fELM after ECH ~20~30 Hz Clear ne & VT drop Similar △WELM No clear effect of ECCD

Large ELMs are triggered by ECH at relatively high ν*

Mitigation of ELMs with Supersonic Molecular Beam Injection After SMBI injection, ELM type changed from type-I like to grassy

ELM pace-making with fast vertical jog ~5 mm of vertical excursion trigger ELMs (~3 mm is marginal) ELM is triggered when plasma moves away with its maximum speed

Multiple ELMs triggered with larger excursion In addition to the normal trigger, larger ELMs are triggered when the vertical position is at lower minimum

Contents Short introduction to KSTAR H-modes L-H transition power threshold Characteristics of H-mode discharges Effect of ECRH on rotation Control of Edge Localized Modes Effect of resonant magnetic perturbation Direct pedestal heating by ECRH ELM mitigation by SMBI ELM pacemaking by Vertical jog Control of Tearing Modes 2424

NTM in KSTAR

Tearing mode stabilisation experiment #6272 : m/n=2/1 tearing appears Ip (kA) R (m) Te (keV) Vtor (km/s) NBI (MW) z (m) Wtot (kJ) Hα NBI (keV) 170 GHz ECH (kW) κ βp RMP (A) 110 GHz ECH (kW) Time (s) Time (s) Time (s) Time (s)

Estimation of Island width from Mirnov coil signals MC1P03 MC1P03 FFT FFT analysis 4/2 mode 2/1 mode 2/1 mode tracking 4.5 4.6 Island width (m)

Determination of Island Location using ECE core edge island Island width (m) R (m)

Preliminary simulation of the island evolution Te From experiment ne, ni assumed Ti from the Weiland model Initial width: 0.55 m Using a2 = 2 Ti (keV) Te (keV) ni (1019m-3) ne (1019m-3) Pech (MW/m2) Time (s) Island width (m) exp. Simul. 2/1 island

Strategy for 2012 experiments (Preliminary) ○ Main Research Direction Controllable H-mode (> 10 s) at ~1 MA ITER relevant/urgent physics issues - ELM mitigation by using RMP, SMBI, ECCD, etc - IOS-related issues: OPEN! Supported by Theory and modelling (ex, WCI) ○ Hardware Priority (mission oriented) NB(+2 MW) -> NB(3.5 MW), LH(0.5 MW), ECH(1 MW) ICRH(1 MW) IRC(In-vessel radial control coil) Thomson(25ch), BES, Reflectometry, Diverter IR

Schedule in 2012(tentative) Evacuation & Wall conditioning Magnet cool-down Plasma experiments SC magnet operation August : Evacuation start Sep. : Cryo-facility operation and magnet cool-down (300 K ~ 4.5 K) Sep. : SC magnet and power supply operation Oct. ~ Nov. : Plasma experiments Dec. : Closing the experiments and magnet warm-up (*) During Jan. to July, New NBI installation