Flow and dynamo measurements in the HIST double pulsing CHI experiment

Similar documents
Current Drive Experiments in the HIT-II Spherical Tokamak

Behavior of Compact Toroid Injected into the External Magnetic Field

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

Current Drive Experiments in the Helicity Injected Torus (HIT II)

Numerical investigation of design and operating parameters on CHI spheromak performance

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

Active Stability Control of a High-Beta Self-Organized Compact Torus

1 IC/P4-5. Spheromak Formation by Steady Inductive Helicity Injection

Confinement of toroidal non-neutral plasma in Proto-RT

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

Oscillating-Field Current-Drive Experiment on MST

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

Confinement of toroidal non-neutral plasma in Proto-RT

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment

The Effects of Noise and Time Delay on RWM Feedback System Performance

REPORT. Numerical Investigation of Transients in the SSPX Spheromak. University of Wisconsin-Madison, Madison, Wisconsin

Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Additional Heating Experiments of FRC Plasma

Non-Solenoidal Plasma Startup in

Abstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N

HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM

Progress in the Plasma Science and Innovation Center

Density Fluctuation Induced Kinetic Dynamo and Nonlinear Tearing Mode Saturation in the MST Reversed Field Pinch

Evaluation of CT injection to RFP for performance improvement and reconnection studies

Magnetic reconnection, merging flux ropes, 3D effects in RSX

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

Equilibrium Evolution in the ZaP Flow Z-Pinch

Turbulence Analysis of a Flux Rope Plasma on the Swarthmore Spheromak Experiment

Density Collapse in Improved Confinement Mode on Tohoku University Heliac

0 Magnetically Confined Plasma

The Levitated Dipole Experiment: Experiment and Theory

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Current Profile Control by ac Helicity Injection

STATUS OF THE HIT-II EXPERIMENTAL PROGRAM

Experimental Investigations of Magnetic Reconnection. J Egedal. MIT, PSFC, Cambridge, MA

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

The RFP: Plasma Confinement with a Reversed Twist

AC loop voltages and MHD stability in RFP plasmas

CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff

DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift )

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center

1 EX/P7-12. Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments

Nonlinear processes associated with Alfvén waves in a laboratory plasma

Imposed Dynamo Current Drive

(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time

Effect of magnetic reconnection on CT penetration into magnetized plasmas

Toroidal confinement of non-neutral plasma. Martin Droba

Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment

Stabilization of a low-frequency instability inadipoleplasma

Total Flow Vector in the C-Mod SOL

Sheared Flow Stabilization in the Z-Pinch

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment

Momentum transport from magnetic reconnection in laboratory an. plasmas. Fatima Ebrahimi

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas

Predictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges

Two Fluid Dynamo and Edge-Resonant m=0 Tearing Instability in Reversed Field Pinch

Flow dynamics and plasma heating of spheromaks in SSX

Characteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

Operational Phase Space of the Edge Plasma in Alcator C-Mod

Overview of Spherical Tokamak Research in Japan

Heating and current drive: Radio Frequency

THE TOROIDAL HELICON EXPERIMENT AT IPR

Experiments with a Supported Dipole

Three-dimensional MHD simulations of counter-helicity spheromak merging in the Swarthmore Spheromak Experiment

Fundamentals of Magnetic Island Theory in Tokamaks

The Sheared Flow Stabilized Z-Pinch

SMR/ Summer College on Plasma Physics. 30 July - 24 August, Introduction to Magnetic Island Theory.

Confinement of toroidal non-neutral plasma

Oscillating Field Current Drive on MST

Large Plasma Device (LAPD)

generalfusion Characterization of General Fusion's Plasma Devices 2015 Nimrod Summer Workshop

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li

Magnetic Self-Organization in the RFP

Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment

Reduction of fluctuations and edge current during PPCD in MST. B. E. Chapman and the MST group

University of Washington

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma

Ion and Electron Heating Characteristics of Magnetic Reconnection in TS-3 and UTST Merging Startup Experiments

MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT

Special topic JPFR article Prospects of Research on Innovative Concepts in ITER Era contribution by M. Brown Section 5.2.2

Electrode Biasing Experiment in the Large Helical Device

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport*

L-H transitions driven by ion heating in scrape-off layer turbulence (SOLT) model simulations

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system

A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg

Sheared flow stabilization experiments in the ZaP flow Z pinch a

A Study of 3-Dimensional Plasma Configurations using the Two-Fluid Plasma Model

Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

MHD. Jeff Freidberg MIT

Transcription:

Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M. Nagata, T. Higashi, M. Ishihara, T. Hanao, K. Ito, K. Matsumoto, Y. Kikuchi, N. Fukumoto, T. Kanki 1) University of Hyogo, Japan Coast Guard Academy 1) Outline 1) Introduction 2) HIST device and diagnostics 3) Experimental topics a) Flows and density profile b) Two-fluid dynamo measurements c) Propagation of magnetic fluctuation 4) Summary

Introduction Coaxial Helicity injection (CHI) is an efficient current-drive and start-up method which was used in many spheromak and ST experiments. A critical issue for CHI is achieving a good energy confinement A new approach of CHI ; Refluxing or Multi-pulsing CHI The multi-pulsing scenario of CHI aims to achieve simultaneously a quasi-steady sustainment and good confinement. ExB rotation Driven Phase 3D MHD simulation Decay Phase Low q ST B t Flow n=1 kink mode time Self organizing

Multi-pulsing CHl for ST configurations The multi-pulsing CHI (M-CHI) discharges on SSPX at LLNL were successfully demonstrated for a high temperature spheromak. (see Ref.[1,2]) Application of the M-CHI to ST configurations What mechanism of current drive is different from spheromak? Flow, Dynamo, Mode structure, etc. High-q ST Low-q ST Spheromak Central open flux column plays an important role in driving a current. A purpose of this experiment is to explore characteristics of the M-CHI driven ST. [1] S. Woodruff, et al. PRL 9, 252-1 (24) [2] E.B. Hooper, PPCF 53, 858 (211).

HIST device and double-pulsing CHI HIST R=.3 m, a=.24 m, A=1.25 n e =.5-1 x 1 2 m -3 T e, T i = 1-4 ev I t < 15 ka S*=R/l i ~1 l i =(c/ω pi )=2~3 cm TF coil current Spheromak, Low q ST: q ~ I tf (= 3 ka) / I t <1 High q ST: q ~ I tf (= ~ 15 ka) / I t >1 Power supply system for double-pulse Formation capacitor banks V = 3-1 kv, C =.6 mf Injection current : I g ~ 3-6 ka Sustainment capacitor banks First pulse : V < 9 V, C = 336 mf Second pulse : V < 9 V, C = 195 mf Injection voltage: V g ~ 4 V Injection current: I g ~ 15 2 ka

Dynamo-Mach Probe Measurement 3-axis flows and 3-axis magnetic fields are simultaneously measured. - Mach probe analysis - Hutchinson model : unmagnetized Ion Mach Number M i : C s =3 km/s (T e =T i ) J up upstream rod current J down downstream rod current V i : ion flow, C s : ion sound velocity, M i : ion Mach number, M c : proportionality constant, T e (T i ): electron (ion) temperature,γ e (γ i ): specific heat ratio for electron (ion), r p : probe radius, ρ i : Larmor radius (~ 1 cm)

Double pulsing CHI discharge Single pulsed discharge 1 st pulse 2 nd pulse Double pulsed discharge Plasma current Averaged density Inner edge Bp Outer edge Bp λ in OFC λ in Core OII Doppler ion temp. By secondly pulsing the MCPG at t = 1.5 or 2.5 ms during the partially decay phase, total plasma current is effectively amplified against the resistive decay. The core current density is generated due to dynamo. The sustainment time has increased up to 6-8 ms which is longer than that in the single CHI case. The edge λ in the OFC is larger than the core λ, causing helicity transport. Doppler ion temperature increases after the second gun pulse.

Flux amplification Second gun pulse Time (ms) High-q ST Poloidal Flux >Bias flux Ψp > Ψ p.bias Bias flux Bp in OFC region Bp.in in closed flux region Flux Amplification A Ψ > 4 ~ 5 # Note that A Ψ includes the OFC Bp.out in closed flux region Injection gun current B p in the closed flux region increases with an increase in the gun current

Internal magnetic field profiles 1 st pulse 2 nd pulse B p (R) M-CHI process Driven phase Decay phase OFC Toroidal current Magnetic field density J t B p and B t Magnetic axis Separatrix Time (ms) OFC Bp is enhanced in the OFC. Magnetic axis moves outwardly. J t becomes from a hollow to a peaked profile. t=2 ms t=6 ms t=7 ms

Diamagnetic properties of Open Flux Column The toroidal field B t in the OFC is decreased from the vacuum field, i.e. diamagnetic due to a high pressure gradient p. OFC radius ~ R diamag Separatrix position R diamag.12~.18 m

Flows and density profiles Poloidal flow v p = Er B 2 B t p B i t 2 enb Poloidal shear flow Diamagnetic current I tf OFC j diamag Toroidal flow Diamagnetic properties of OFC P Radial electric field E r ion E r ỊI t Density ( I sat ) negative edge E r electron Steep gradient OFC E r en i p Z i i ( v B p t v t B p )

Two fluid dynamo effect Generalized Ohm s s law ~ ~ ~ η j E = v B ) + < v~ B > ( j B ) /en < j B > ηj E η j = E + v B j B ( Hall dynamo /en+ ~ ~ ~ ~ ~ =< v ~ B > < j B > /en < v B > MHD dynamo ~ ~ ~ E v j /en ~ B e B ve = + 2 2 ExB drift # Diamagnetic dynamo term does not appear explicitly in the parallel meanfield Ohm s law ~ ~ < pe B > Diamagnetic dynamo en B * Private communication with Dr. K. McCollam B p~ enb Diamagnetic drift e p e /en Electron dynamics e je j 2 i 2 B B /en # Diamagnetic current j diamag due to electron and ion diamagnetic drift contributes on ~ B ~ Hall dynamo term p ~ B ~ p i

Hall and MHD dynamo measurement Measurement of three components of fluctuating velocity, current density and magnetic field at a radial position r θ z Hall dynamo probe (5x5x5 mm) Incorporating Rogowski loop and flux loop Hall dynamo probe MHD dynamo probe E E t t =< δv δb =< δj δb > > t t =< δv =< δj z z δb δb r r δv δj r r δb δb z z > > out of phase in phase

Dynamo balances Ohm s s law MHD Hall Toroidal current density MHD 1 st st pulse 2 nd nd pulse Core Core Core OFC ηj ~ ~ ~ ~ E = < v B > < j B > η spitzer Parallel mean-field Ohm's law = MHD dynamo Ψ p ( r) E ( r) = V /L g t 2 π r η OFC region = 5.22 1 5 η Z eff Hall dynamo (kt ) 3 / 2 2 ~ 6 1 5 Core region e ln /en I sat Λ Ωm Hall Toroidal current density OFC OFC V E ηj g 1 ~ 2 1 ~ 3 ~ 9 1 2 V V/m V/m ~ ~ ~ < v~ B > < j > /en V/m B V g E ηj 2 V V/m 4 ~ 12 V/m 6~ 14V/m

Radial profile of dynamo electric field ~ ~ < v B > OFC ~ ~ < j B Core > /en Hall dynamo Collisional drag of electrons on the ions accelerates the ions in the core. Electrons become slow down due to anti-dynamo E MHD MHD dynamo Anti-MHD dynamo Ions are accelerated due to E Hall in the direction of the current in the OFC. Hall dynamo driven current in the OFC is the same direction as the mean current. MHD anti-dynamo electric field in the OFC reduces the mean current. Electron locking model [1] δω ce τ ie >δ/r [1] T.R. Jarboe et al., Nucl. Fusion 51 6329 (211).

Radial propagation of magnetic fluctuation Gun OFC region Closed flux region λ gun > λ OFC > λ core Helicity flow 2nd-pulse f (khz) #1416 R (mm) OFC Second-gun-pulse 8 khz 2-4 khz ~ B ( t ) #1416 Red R=.25m Black R=.1m R=.75 m R=.175 m R=.25 m R=.3 m 2-4 khz 8 khz Time (ms) Time (ms)

Axial propagation of magnetic fluctuation ~ B ( t ) Propagation by Alfven speed Z (m) midplane Second-gun-pulse #1416 ~ B ( t ) ~8 khz Red Z=.784m Black Z=.216 m Time (ms) Z=.926 (m) Z=.784 (m) Z=.642 (m) Z=.5 (m) Gun Second-gun-pulse f (khz) 8 khz Time (ms) #1416

Summary The HIST device has been developed towards high-β and quasi-steady-state sustainment of high-q and low-q ST plasmas by Multi-pulsing CHI method. We have successfully demonstrated the flux/current amplification and sustainment of the plasmas in the double gun pulse experiment. We have observed the poloidal flow shear between the OFC region and the closed flux region. The ion diamagnetic drift due to a steep density gradient observed there could account for the flow reversal. We have measured simultaneously the Hall and MHD dynamo spatial profile. The relative contributions of the different dynamo electric field on the driven current have been investigated to verify mean Ohm s law balance. The Hall dynamo acts to generate the mean current density in the both regions, although anti-mhd dynamo is effective in the OFC region. The observed spatial propagation of magnetic fluctuations suggests that helicity is transported to the core from the OFC connected with the gun electrodes during the driven-phase in the multi-pulsing CHI.