H. Y. Lee, J. W. Lee, J. G. Jo, J. Y. Park, S. C. Kim, J. I. Wang, J. Y. Jang, S. H. Kim, Y. S. Na, Y. S. Hwang

Similar documents
The ECH experiments in VEST(Versatile Experiment Spherical Torus)

Status and Plan for VEST

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

Observation of Electron Bernstein Wave Heating in the RFP

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

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

Observation of Electron Bernstein Wave Heating in the RFP

Mode-converted Electron Bernstein Waves

Princeton Plasma Physics Laboratory

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

ICRF Physics in KSTAR Steady State

Full-wave feasibility study of magnetic diagnostic based on O-X mode conversion and oblique reflectometry imaging

Microwave Experiments on Prairie View Rotamak

2.3 PF System. WU Weiyue PF5 PF PF1

Faster, Hotter MHD-Driven Jets Using RF Pre-Ionization

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

Varying Electron Cyclotron Resonance Heating to Modify Confinement on the Levitated Dipole Experiment

CW RF cesium-free negative ion source development at SNU

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

Helicon Wave Current Drive in KSTAR Plasmas

Long Pulse EBW Start-up Experiments in MAST

Wall Conditioning Strategy for Wendelstein7-X. H.P. Laqua, D. Hartmann, M. Otte, D. Aßmus

Status of the rf Current Drive Systems on MST

Improvements in the fast vertical control systems in KSTAR, EAST, NSTX and NSTX-U

Non-Solenoidal Startup via Local Helicity Injection and Edge Stability Studies in the Pegasus Toroidal Experiment

PLASMA STUDIES AT HIGH NORMALIZED CURRENT IN THE PEGASUS EXPERIMENT

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

Study of Plasma Equilibrium during the AC Current Reversal Phase on the STOR-M Tokamak

Abstract. *Supported by U.S. DoE grant No. DE-FG02-96ER Pegasus Toroidal Experiment University of Wisconsin-Madison

TOKAMAK T-15MD: experience of scientific and technical project realization in RUSSIA

National Fusion Research Institute a. Princeton Plasma Physics Laboratory

Structural Analysis of High-field-Side RF antennas during a disruption on the Advanced Divertor experiment (ADX)

3D-MAPTOR Code for Computation of Magnetic Fields in Tokamaks

Local Helicity Injection Startup and Edge Stability Studies in the Pegasus Toroidal Experiment

High Frequency Gyrotrons and Their Applications

Interdependence of Magnetic Islands, Halo Current and Runaway Electrons in T-10 Tokamak

Supported by. Overview of Transient CHI Plasma Start-up in NSTX. Roger Raman University of Washington

Recent progress of 170 GHz Gyrotron in KSTAR

Gyung-Su Lee National Fusion R & D Center Korea Basic Science Institute

Status of the KSTAR Superconducting Magnet System Development

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

KSTAR Construction and Commissioning

Coupling to the electron Bernstein wave using a phased array of waveguides in MST reversed field pinch

2. Composing and characteristics of EAST

Plasma Confinement by Pressure of Rotating Magnetic Field in Toroidal Device

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

Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas

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

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

Development of a Multi-Purpose, Multi-Frequency Gyrotron for DEMO at KIT

Abstract. * Supported by U.S. D.O.E. Grant DE-FG02-96ER54375

Radiofrequency Current Drive Experiments in MST

CT-7Ra Development of Gyrotron and JT-60U EC Heating System for Fusion Reactor

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

Fault Analysis of ITER Coil Power Supply System

Particle Simulation of Lower Hybrid Waves in Tokamak Plasmas

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

Particle Simulation of Radio Frequency Waves in Fusion Plasmas

Comparison of toroidal viscosity with neoclassical theory

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

Study of Ion Cyclotron Emissions due to DD Fusion Product Ions on JT-60U

3.10 Lower Hybrid Current Drive (LHCD) System

Resonant and Non-resonant type Pre-ionization and Current Ramp-up Experiments on Tokamak Aditya in the Ion Cyclotron Frequency Range

Observation of Toroidal Flow on LHD

2. Achievement of reliable long pulse operation of 1 MW 170 GHz gyrotron

Profile Scan Studies on the Levitated Dipole Experiment

Development of the 170GHz gyrotron and equatorial launcher for ITER

Development of the frequency scanning reflectometry for the registration of Alfvén wave resonances in the TCABR tokamak

Electron Bernstein Wave Heating and Emission in the TCV Tokamak

Overview and Initial Results of the ETE Spherical Tokamak

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

SUMMARY OF THE EXPERIMENTAL SESSION EC-10 WORKSHOP

Launcher Study for KSTAR 5 GHz LHCD System*

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

2.2 MW Operation of the European Coaxial-Cavity Pre-Prototype Gyrotron for ITER

Stability Analysis of C-band 500-kW Klystron with Multi-cell. Output cavity

Design of a new 18 GHz ECRIS for RIKEN RIBF

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

Investigation of compact toroid penetration for fuelling spherical tokamak plasmas on CPD

ECRF Heating on CS Reactors

Recent Activities on SST-1 and ADITYA-U Tokamaks )

Operational progress of 170GHz 1MW ECH system in KSTAR

Novel Reactor Relevant RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies

Power-stabilization of high frequency gyrotrons using a double PID feedback control for applications to many high power THz spectroscopy

X- AND 0-MODE ELECTRON CYCLOTRON HEATING BREAKDOWN AND STARTUP IN TCA

Compact Torus Injection for Fuelling* C. Xiao, A. Hirose, STOR-M team Plasma Physics Laboratory University of Saskatchewan

Control and data acquisition system for SCR-1 Stellarator

Electromagnetic Field Simulation for ICRF Antenna and Comparison with Experimental Results in LHD

Contributions of Advanced Design Activities to Fusion Research

3D modeling of toroidal asymmetry due to localized divertor nitrogen puffing on Alcator C-Mod

Construction of 0.5-MW prototype PAM for KSTAR LHCD system

Importance of edge physics in optimizing ICRF performance

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

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

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

Variation of N and its Effect on Fast Wave Electron Heating on LHD

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

Magnetics and Power System Upgrades for the Pegasus-U Experiment

3.4 Poloidal Field Power Supply Systems for the EAST Steady State Superconducting Tokamak

A modular Cap bank for SSPX 1

Transcription:

Study on EBW assisted start-up and heating experiments via direct XB mode conversion from low field side injection in VEST H. Y. Lee, J. W. Lee, J. G. Jo, J. Y. Park, S. C. Kim, J. I. Wang, J. Y. Jang, S. H. Kim, Y. S. Na, Y. S. Hwang Center For Advanced Tokamak Study Department of Nuclear Engineering Seoul National University Korea-Japan Workshop on H&CD December 15 th, 2016 NUPLEX, Dept. of Nuclear, Seoul National University, San 56-1, Shillim-dong, Gwanak-gu, Seoul 151-742, Korea brbbebbero@snu.ac.kr

Introduction VEST : the first Spherical Torus in Korea Versatile Experiment Spherical Torus Objectives Basic research on a compact, high- ST (Spherical Torus) Study on innovative start-up, non-inductive H&CD, and innovative divertor concept, etc Specifications Initial Phase Future Chamber Radius [m] 0.8 : Main Chamber 0.6 : Upper & Lower Chambers Chamber Height [m] 2.4 Toroidal B Field [T] 0.1 0.3 Major Radius [m] 0.43 0.4 Minor Radius [m] 0.33 0.3 Aspect Ratio >1.3 >1.3 Plasma Current [ka] ~100 ka 100 Elongation ~1.6 2.5 Safety factor, q a ~3.5 ~3 2/15

Introduction Motivation Electron Cyclotron Heating(ECH) is widely used for various purposes in fusion device that the pre-ionization, local heating and current drive. Especially non-inductive current drive and startup using ECH is essential for Spherical Torus (ST) which has lack of space for the center stack. But ECH in ST shows the limitations due to low toroidal field. An EBW(Electron Bernstein Wave) which has no cutoff density, has been proposed as a promising alternative for heating and current drive in ST that it is impossible for ECH due to density limit. EBW Pros Cons OXB (O cutoff & UHR) OXB (CS & UHR) Excellent results in theory and experiment Complex Scenario Density fluctuation Angular dependant Complex Scenario Need : polarizer Limit of O cutoff XB (UHR) Simple design Single Mode conversion Limit of R cutoff tunneling effect Control on density profile Device MAST, NSTX, QUEST LATE, TST-2, CDX-U 3/15

Experimental Setup in VEST 2.45 GHz ECH/EBW System of VEST 1.5 Coil Geometry (a) (b) 1 0.5 Z (m) 0 2.45GHz ECH 2.45 GHz ECH/EBW system (a) CW 6 kw (b) Pulse 10 kw -0.5-1 -1.5 0 0.2 0.4 0.6 0.8 1 R (m) CW ECH/EBW System Commercial microwave power supply (6 kw 2.45 GHz: 1ea) Low field side launching Vertical injection(x/o) Pulse ECH/EBW System Cost-effective homemade magnetron power supplies (10 kw : 1ea, 3 kw : 4ea) Low field side launching Vertical injection(x/o) Pulse duration, trigger time 4/15

Experimental Setup in VEST 2.45 GHz pulse ECH System of VEST Filament Heating 10 kw Magnetron Cathode MOSFET Switch Anode Electro magnet Antenna 20 kω Pneumatic Switch 12 kv 220 uf 110 kω Pneumatic Switch 100 Ω 25000 20000 6kW CW Forward Power 10kW Pulse Forward Power 10kW Pulse Reflect Power 13 V 53 A 15000 10000 5000 0 390 392 394 396 398 400 402 404 406 408 410 5/15

EBW Pre-ionization Experiments in VEST ECH Pre-ionization Experiment with Pure TF 2.70E+017 2.40E+017 2.10E+017 Toroidal field ~ 0.1 T at R = 0.2 m ECR TF 3.8 ka with ECH 6 kw TF 3.8 ka with ECH 10 kw Toroidal field current ~ 0.1 T at R = 0.45 m 2.70E+017 2.40E+017 2.10E+017 ECR TF 8.2 ka with ECH 6 kw TF 8.2 ka with ECH 10 kw Density (#/m3) 1.80E+017 1.50E+017 1.20E+017 9.00E+016 6.00E+016 3.00E+016 Density (#/m3) 1.80E+017 1.50E+017 1.20E+017 L cutoff 9.00E+016 UHR R cutoff6.00e+016 3.00E+016 L cutoff UHR R cutoff 0.00E+000 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Radius (m) Pure TF + ECH pre-ionization experiment 0.00E+000 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Radius (m) In case of 3.8 ka, high density plasma generates near ECR with ECH 6 & 10 kw In case of 8.2 ka, over dense plasma generation over L cut off density and plasma density peak exists near UHR : Collisional damping with XB conversion In case of 3.8 ka, the density peak exists near inboard but in case of 8.2 ka, the mode conversion efficiency increases with steep density gradient near UHR and collisional damping of EBW makes the density peak 6/15

EBW assisted Start-up Experiments in VEST TPC Start-up Scheme Field Null Configuration Significant enhancement of pre-ionization under TPC (Trapped Particle Configuration) 1.5 1.2 Inner Wall Trapped Particle Configuration Field Null Configuration TF only B T ~0.05 T at R=0.4 m Outer Wall Trapped Particle Configuration n e [10 17 m -3 ] 0.9 0.6 0.3 0.0 LFSO 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 R [m] Prompt I p Initiation under TPC Save Voltsec consumption & Stable Decay index LFSX 7/15

Density (#/m3) 2.50E+017 2.00E+017 1.50E+017 1.00E+017 5.00E+016 EBW assisted Start-up Experiments in VEST Start-up Experiment with low TF (~4 ka) (1) ECR TF only 6kW TPC 3kW TPC 5kW TPC 6kW TPC 6+10 kw L cutoff UHR R cutoff Current Rampup Rate (MA / s) 5.0 4.5 4.0 3.5 0.00E+000 0.2 0.3 0.4 0.5 0.6 0.7 0.8 only TF 6 kw TPC 3 kw TPC 5 kw TPC 6 kw Enhancement of pre-ionization under TPC ( Trapped Particle Configuration) The enhanced plasma density overcomes the cutoff density : Collisional damping of EBW (Electron Bernstein Wave) via direct XB mode conversion from the low field side injection The plasma density increases rapidly after encountering UHR resonance layer In case of higher ECH power 16 kw, the density peak exists near outboard side due to converted EBW collisional damping The enhanced pre-ionization plasma near inboard side which has relatively strong electric field must be helpful for successful plasma current formation. The enhanced plasma density has on influence to the plasma current ramp-up rate with same loop voltage ~ 1.5 V 3.0 8/15

EBW assisted Start-up Experiments in VEST Start-up Experiment with low TF (~4 ka) (2) 650 Current Rampup Rate (ka / s) 600 550 500 450 400 TPC 3kW TPC 5kW TPC 6kW Based on these experimental results, extremely low loop voltage startup scheme is suggested. The plasma current has not been generated with only TF case. With low loop voltage, the pre-ionization density affects to the plasma current ramp-up rate dominantly. With extremely low electric field ~0.16 V/m, the startup experiment has been performed successfully with enhanced pre-ionization plasma via EBW collisional heating. The TPC start-up scheme has the feasibility applicable to low electric field start-up machine including KSTAR and ITER(~0.3 V/m). 9/15

Density (#/m 3 ) 4.00E+017 3.50E+017 3.00E+017 2.50E+017 2.00E+017 1.50E+017 1.00E+017 5.00E+016 EBW assisted Start-up Experiments in VEST Start-up Experiment with high TF (~8.3 ka) (1) ECR 0.00E+000 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Radius (m) TPC with ECH 6 kw TPC with ECH 6&10 kw L cutoff UHR R cutoff In case of only TF with 6 kw ECH power, density peak exists near outboard side due to collisional damping of EBW via direct XB mode conversion from LFS injection. Solenoid free startup scheme utilizing outer PF coils (6&9) is suggested The loop voltage of 6~7 V has been adopted to the over-dense pre-ionization plasma utilizing TPC but the plasma current has not been grown up. The lower plasma resistivity for plasma current formation is necessary for successful solenoid free start-up to overcome the vertical field. Loop voltage [V] 8 6 4 2 0 403 404 405 406 407 408 Time [msec] R~0.66 R~0.68 R~0.70 R~0.72 R~0.74 R~0.76 10/15

Plasma Current [ka] 0.0-0.4-0.8-1.2 11/15 EBW assisted Start-up Experiments in VEST Start-up Experiment with high TF (~8.3 ka) (2) R = 0.75 m, a = 0.2 m 402.8 403.0 403.2 403.4 403.6 403.8 404.0 The simulation for simple LR circuit with loop voltage from outer PF coils Shape : Circular single filament current with major and minor radius This simulation result with assumption of no wall More powerful enhancement of pre-ionization is necessary for formation of plasma current I p overcoming B v 2.63158E-6 2.3907E-5(TPC 6+10 kw) 2.3907E-5(a=0.05m) Time [ms] Estimation : over 40 ev T e and 5 10 17 #/m 3 (resistivity : T e dominant) If the plasma current is generated, the plasma moves inward and the current and shape increases with help of negative voltsec consumption with decrease of external inductance. Additional simulation and start-up experiments will be investigated for CS-free start-up. Plasma Current [ka] -0.4-0.8-1.2-1.6-2.0-2.4-2.8-3.2-3.6 0.4 0.0 R = 0.70 m, a = 0.50 m I p overcoming B v 1.45607E-5 (TPC 6+10kW) 3.26116E-5 (TPC 6kW) 1.45607E-5 (a=0.1m) -4.0 402.8 403.0 403.2 403.4 403.6 403.8 404.0 Time [ms]

EBW Heating Experiments in VEST EBW collisional heating during startup Density (#/m 3 ) 1.60E+018 1.40E+018 1.20E+018 1.00E+018 8.00E+017 6.00E+017 4.00E+017 Additional 10 kw ECH on TPC Startup with 6 kw (R=0.5 m) TPC Startup with 6&10 kw (R=0.5 m) Plasma Current (A) 25000 20000 15000 10000 TF 8.2 ka TPC Startup with 6 kw (R = 0.5 m) TF 8.2 ka TPC Startup with 6&10 kw (R = 0.5 m) 2.00E+017 5000 0.00E+000 398 400 402 404 406 408 410 412 Time (ms) 0 395 396 397 398 399 400 401 402 403 404 405 406 407 408 409 410 Time (ms) EBW collisional heating occurs during TPC startup The additional 10 kw pulse ECH injection has occurred at 402 ms The feasibility of strong heating in the closed flux surface (R=0.5 m) is confirmed and EBW collisional damping (density increase). Electron temperature does not change : Low collisionality is necessary High electron temperature and low impurity for reducing the effect of collisional heating 12/15

Density (#/m3) Plasma Current (ka) 5.00E+018 4.50E+018 4.00E+018 3.50E+018 3.00E+018 2.50E+018 2.00E+018 1.50E+018 60 55 50 45 40 35 30 25 20 15 10 5 EBW Heating Experiments in VEST EBW heating Experiments (1) 1st ECR 1.00E+018 406(on) 406(off) 5.00E+017 408(on) 0.00E+000 408(off) 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0 400 401 402 403 404 405 406 407 408 409 410 411 412 Time (ms) 2nd ECR Radius (m) off on 3rd ECR Temperature (ev) 60 55 50 45 40 35 30 25 20 1st ECR 2nd ECR 15 406(on) 10 406(off) 5 408(on) 0 408(off) 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Radius (m) Boronization (impurity removal) and high plasma current (high electron temperature) Additional 10 kw MW injection at 402 ms 3rd ECR No change along the electron density profile with additional MW no collisional damping The electron temperature rises two times near 3 rd harmonics the first position after mode conversion 13/15

EBW Heating Experiments in VEST EBW heating Experiments (2) Temperature (ev) 60 55 50 45 40 35 30 25 20 1st ECR 2nd ECR 3rd ECR 15 406(on) 10 406(off) 5 408(on) 408(off) 0 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Density (#/m3) 5.00E+018 4.50E+018 4.00E+018 3.50E+018 3.00E+018 2.50E+018 2.00E+018 1.50E+018 1.00E+018 5.00E+017 406 ms 408 ms 0.00E+000 0.2 0.3 0.4 0.5 0.6 0.7 0.8 The Electron heating of EBW via direct XB MC from LFS The electron temperature arises at 406 ms but has not been changed at 408 ms. Hollow density profile due to fast plasma current ramp-up rate 406 ms : ramp-up phase steep density gradient 408 ms : current peak phase broad density profile The more detailed electron heating experiments will be performed along the UHR and ECR position for the change of local electron heating 14/15

Summary The pre-ionization plasma with TPC has been enhanced assisted by EBW collisional heating and the density peak has been observed near inboard and outboard side along the toroidal field. Based on the TPC pre-ionization results, two start-up schemes are suggested for extremely low loop voltage start-up and solenoid free start-up utilizing outer PF coils. The plasma current ramp-up rate is determined by the enhanced pre-ionization plasma density and based on the results, the startup experiments have been performed successfully with the extremely low loop voltage of ~ 0.2 V/m. The solenoid free startup experiments utilizing outer PF coils have been performed but the necessity of the more intensified pre-ionization plasma with analyzing the plasma resistivity has been addressed. The EBW heating experiments during ohmic discharges have been conducted with low collisionality plasma and it is observed that the electron temperature arise near the 3 rd harmonic ECR from EBW via direct XB mode conversion from low field side injection. 15/15

Reference [1] V. F. Shevchenko et al., Nucl. Fusion, 50 022004 (2010) [2] A. K. Ram et al., Phys. Plasmas, 7 4084 (2000) [3] Idei Hiroishi et al., FEC2012, EX/P6-17 (2012) [4] Uchida Masaki et al., FEC2012, EX/P6-18 (2012) [5] S. Shiraiwa et al., Phys. Rev. Lett., 96, 185003 (2006) [6] G. Taylor et al., Rev. Sci. Instrum. 72, 285 (2001) [7] S. Pesic, Physica C, 125, 118-126 (1984) [8] Josef Preinhaelter et al., Rev. Sci. Instrum. 77, 10F524 (2006) [9] S. J. Diem et al., Rev. Sci. Instrum. 79, 10F101 (2008) [10] S. H. Kim et al., Physics of Plasmas, 21, 062108 (2014) 16/15

Backup Thank you for your attention! 17/15