Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA Burrell, K.H. General Atomics PO Box San Diego, CA

Similar documents
GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

L-to-H power threshold comparisons between NBI and RF heated plasmas in NSTX

Potentials, E B drifts, and uctuations in the DIII-D boundary

Scaling of divertor heat flux profile widths in DIII-D

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

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

GA A27806 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT

Scaling of divertor heat flux profile widths in DIII-D

A Study of Directly Launched Ion Bernstein Waves in a Tokamak

Statistical Analysis of Fluctuation Characteristics at High- and Low-Field Sides in L-mode SOL Plasmas of JT-60U

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

SPECTRUM AND PROPAGATION OF LOWER HYBRID WAVES IN THE ALCATOR C TOKAMAK

Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection

GA A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES

GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D

GA A27418 THE ROLE OF ZONAL FLOWS AND PREDATOR- PREY OSCILLATIONS IN THE FORMATION OF CORE AND EDGE TRANSPORT BARRIERS

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT

Phase ramping and modulation of reflectometer signals

Particle transport results from collisionality scans and perturbative experiments on DIII-D

Transport Improvement Near Low Order Rational q Surfaces in DIII D

GA A26474 SYNERGY IN TWO-FREQUENCY FAST WAVE CYCLOTRON HARMONIC ABSORPTION IN DIII-D

GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.

Studies of Turbulence and Transport in Alcator C- Mod H-Mode Plasmas with Phase Contrast Imaging and Comparisons with GYRO*

Blob sizes and velocities in the Alcator C-Mod scrapeoff

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

Progress of Confinement Physics Study in Compact Helical System

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

ICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

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

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Turbulence Measurements with the Upgraded Phase Contrast Imaging Diagnostic in Alcator C-Mod

Plasma Science and Fusion Center

ELMs and Constraints on the H-Mode Pedestal:

IMPACT OF EDGE CURRENT DENSITY AND PRESSURE GRADIENT ON THE STABILITY OF DIII-D HIGH PERFORMANCE DISCHARGES

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas

Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

Role of Magnetic Configuration and Heating Power in ITB Formation in JET.

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX

Spontaneous Core Toroidal Rotation in Alcator C- Mod L-Mode, H-Mode and ITB Plasmas.

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D

C-Mod Transport Program

Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod

Spatial, temporal and spectral structure of the turbulence-flow interaction at the L-H transition

Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod

GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK

GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

Simulation of Double-Null Divertor Plasmas with the UEDGE Code

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

GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE STABILITY IN DIII D

Pedestals and Fluctuations in C-Mod Enhanced D α H-modes

On the ρ Scaling of Intrinsic Rotation in C-Mod Plasmas with Edge Transport Barriers

Edge Impurity Dynamics During an ELM Cycle in DIII D

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Edge Zonal Flows and Blob Propagation in Alcator C-Mod P5.073 EPS 2011

Characteristics of the H-mode H and Extrapolation to ITER

UNDERSTANDING TRANSPORT THROUGH DIMENSIONLESS PARAMETER SCALING EXPERIMENTS

Study of Enhanced D α H-modes Using the Alcator C-Mod Reflectometer

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a)

Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas

Triggering Mechanisms for Transport Barriers

Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge, MA USA

GA A26866 REDUCED ELECTRON THERMAL TRANSPORT IN LOW COLLISIONALITY H-MODE PLASMAS IN DIII-D AND THE IMPORTANCE OF SMALL-SCALE TURBULENCE

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges

Simulation of Plasma Flow in the DIII-D Tokamak

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

GA A27290 CALCULATION OF IMPURITY POLOIDAL ROTATION FROM MEASURED POLOIDAL ASYMMETRIES IN THE TOROIDAL ROTATION OF A TOKAMAK PLASMA

Nonlinear Gyrokinetic Simulations of Ion Turbulence in Impurity Seeded and High Density Toroidal Plasmas

proposed [6]. This scaling is found for single null divertor configurations with the VB

Measurement of lower hybrid waves using microwave scattering technique in Alcator C-Mod

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

Electron Bernstein Wave Heating in the TCV Tokamak

Effect of ion B drift direction on density fluctuation poloidal flow and flow shear

IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT IN DIII-D

ICRF Mode Conversion Flow Drive on the Alcator C Mod Tokamak

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod

Role of Flow Shear in Enhanced Core Confinement

PSFC/JA D.R. Ernst, N. Basse, W. Dorland 1, C.L. Fiore, L. Lin, A. Long 2, M. Porkolab, K. Zeller, K. Zhurovich. June 2006

Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D

Predicting the Rotation Profile in ITER

Overview Impact of 3D fields (RMP) on edge turbulence and turbulent transport

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL.

Curvature transition and spatiotemporal propagation of internal transport barrier in toroidal plasmas

Overview the CASTOR Fast Particles experiments

The role of zonal flows and predator-prey oscillations in triggering

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles

Study of Laser Plasma Interactions Using an Eulerian Vlasov Code

Transcription:

PFC/JA-95-28 Edge Turbulence Measurements during the L- to H-Mode Transition by Phase Contrast Imaging on DIII-Dt Coda, S.; Porkolab, M.; Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA 02139 Burrell, K.H. General Atomics PO Box 85608 San Diego, CA 92186-9784 August 1995 Presented at the Fifteenth International Conference on Plasma Physics and Controlled Nuclear Fusion Research, Seville, Spain, 26 September - 01 October 1994, IAEA-CN- 60/A-1-II-2, to be published in the Proceedings. t This work was supported by the U.S. Department of Energy Contract No. DE-AC02-78ET51013.

Edge Turbulence Measurements During the L- to H-Mode Transition by Phase Contrast Imaging on DIII-D* S. Codat and M. Porkolab Department of Physics and Plasma Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA K.H. Burrell General Atomics, P.05ox 85608, San Diego, California 92186-9784, USA 1. Introduction A C0 2 -laser imaging diagnostic measures the vertical line integrals of the density fluctuations at 16 radial locations within a 7.6-cm-wide region at the outer edge of the DIII-D tokamak [1]. The phase-contrast technique [2] provides a flat response to wave numbers in the range 1-16 cm' [3] and is mostly sensitive to radial wave vectors [4]. This last property ensures that fluctuations are detected essentially in the plasma frame, since the E x B drift associated with the radial electric field is mainly in the poloidal direction. The radial resolution is 0.5 cm, the data acquisition bandwidth is 1 MHz, and the density sensitivity is on the order of 109 cm- 3. The DIII-D Phase Contrast Imaging (PCI) diagnostic has been employed in the study of plasma turbulence, particularly at the transition from L- to H-mode. Past work has shown that the average amplitude of the line-integrated fluctuations in the plasma is reduced at the onset of the H-mode, in agreement with measurements by other diagnostics in DIII-D and elsewhere [5]. In the frequency domain, two distinct spectral regions were identified: a low-frequency ($20 khz) band, which is generally unaffected by the transition, and a broad high-frequency region, which is strongly suppressed in H-mode. In addition, it was determined through spatial analysis that the L-mode fluctuations have a nonzero average group velocity in the inward direction [4]. In this paper we report on measurements of turbulence carried out during a study of low-power L- to H-mode transitions [6]. As the input power approaches the threshold for H-mode, the transition occurs on a progressively slower time scale. The new results are consistent with past observations in L-mode and in the fully developed H-mode; novel features emerge, however, in the transient phase immediately following the transition. The phenomenology of these events, which lack a theoretical explanation at present, will be discussed in the next section. * This work was supported by the U.S. Department of Energy under Grant No. DE-FG02-91ER54109 at MIT and Contract No. DE-AC03-89ER51114 at General Atomics. t Present address: General Atomics, San Diego, CA 92186-9784, USA 1

2. Slow L- to H-mode transitions This experiment was carried out in lower-single-null diverted plasmas with a toroidal magnetic field of 2.1 T, a plasma current of 1.37 MA, and a line-averaged density of 3.2x 1013 cm-3. The neutral-beam power was 2 MW, approximately 30% higher than the threshold for obtaining H-mode [6]. Data from 8 PCI chords were acquired at a rate of 500 ksamples/s; the intersections of the PCI chords with the midplane scanned the region from 2.5 cm inside to 2.5 cm outside the separatrix. The time histories of the rms fluctuation levels on two chords, one of which intersects the plasma while the other lies entirely in the scrape-off layer (SOL), are shown in Fig. 1, along with a De, emission signal for reference. At the start of the drop in the DQ trace, which signals the onset of the H-mode, the fluctuation level on the plasma chord decreases rapidly, reaching a minimum in ~50 Ps. Only a slight drop is observed on the SOL chord. After a quiescent phase of ~0.6 ms, the fluctuation level rises again, to a value similar to that of L-mode on the plasma chord, and to a substantially larger value on the SOL chord. This turbulent phase subsides slowly, on a 20-30 ms time scale. In the final H-mode phase, which begins approximately when the D, signal completes its descent, the fluctuation amplitude is lower than in L-mode on the plasma chord and of the same order as in L-mode on the SOL chord, in accord with past measurements. (a) R-RSEP = -0.4 cm (b) E R-RSEP =+1.1 Cm 0 U Edge Da emission A I Separatrix 1515 1525 1535 1545 Time (ms) Fig. 1. (a) Rms line-integrated fluctuations on PCI chords, 0.4 cm inside (top) and 1.1 cm outside the separatrix (middle), and D, emission signal (bottom). The vertical line denotes the time of the L-H transition. (b) Detail of field lines, with exaggerated curvature, and of the PCI chords used in left-hand plot. The uncertainty on the position of the separatrix is ±0.5 cm. )

Figure 2 shows the frequency autopower spectra of the fluctuation signals in logarithmic scale on the same two chords, calculated at three different times, respectively in L-mode, in early H-mode, and in late H-mode. In L-mode, least-squares fits to inverse power functions for all 8 chords yielded exponents in the range 1.7-2.3 with reduced X 2 values smaller than 1. The spectrum becomes more irregular in early H-mode and is also shifted toward higher frequencies. This may be partly due to residual Doppler shifts from the increased E x B velocity [5]. The average level is similar to that in L-mode on all plasma chords and in the deep SOL, whereas it is considerably larger at the SOL location shown in Fig. 2. It is possible in fact that the early-h-mode turbulence is limited to the SOL; by contrast, the L-mode fluctuations peak 1-2 cm inside the separatrix. This dissimilarity may account for the reduced transport in the plasma in early H-mode. Finally, the fluctuation level in late H-mode is considerably lower than that in L-mode on all plasma chords, whereas the two are of the same order on all SOL chords; these results are in agreement with past measurements. An analysis of spatial correlations in the various phases confirms that correlations are generally weaker in late H-mode than in L-mode and that the L-mode turbulence is predominantly inward propagating. The level of correlation in early H-mode is of the same order as that in L-mode, or in some cases greater, but no net propagation is observed in H-mode. These conclusions are evidenced by Fig. 3, which shows the envelope of the correlation coefficient for two selected pairs of plasma chords. In view of the suggested coexistence of two or more independent components in the spectrum of the turbulence, it is difficult to define simple global parameters such as correlation lengths. Indeed, the correlation coefficient is not always a decreasing function of the spatial separation. The present data will be analyzed further in the future in an effort to put these considerations on a more quantitative footing. R-RSEP = -0.4 cm R-RSEP = +1.1 cm 10 10-102 E - 5 1c(b 10 10-44// 10 10-0 160 200 0 100 200 Frequency (khz) Frequency (khz) Fig. 2. Frequency autopower spectra in logarithmic scale of PCI signals from chords (a) 0.4 inside and (b) 1.1 outside the separatrix. The solid line is for L-mode, the dashed line is for early H-mode, and the dotted line is for late H-mode. Estimates were calculated on 100 realizations. The shaded area lies below the instrumental noise (signal-to-noise ratios are between 1 and 400). 3

R-RSEP = -1.9/-2.4 cm R-RSEP = -0.4/-1.9 cm 1 0.,-- -,,,, I I (a) f~,~ V. U0 -' -. I I I I An0. I. -30-20 -10 0 10 20 30-30-20-10 0 10 20 30 At (pis) At (As) Fig. 3. Envelope of the correlation coefficient between PCI chords (a) 1.9 and 2.4 cm inside the separatrix, and (b) 0.4 and 1.9 cm inside the separatrix. The solid line is for L-mode, the dashed line is for early H-mode, and the dotted line is for late H-mode. Averaging time is 10 ms. Positive skewness indicates inward group velocity. Acknowledgments 10 " 4 sell" I "'1816- We wish to thank Dr. R.A. Moyer for planning and directing the experiment in the course of which our measurements were carried out. The collective role of the DIII-D team in the execution of that experiment is also gratefully acknowledged. (b).0 " " - %*s~g~g OW References [1] Coda S. and Porkolab M. Rev. Sci. Instrum. 66 454 (1995) [2] Weisen H. Rev. Sci. Instrum. 59 1544 (1988) [3] Coda S., Porkolab M. and CarIstrom T.N. Rev. Sci. Instrum. 63 4974 (1992) [4] Coda S. and Porkolab M in Proc. 21th EPS Conference on Controlled Fusion and Plasma Physics, Montpellier, France, Vol. 18B, Part 11 (1994), p. 854 [5] Burrell K.H. Plasma Phys. and Contr. Fusion 36 A291 (1994) [6] Moyer R.A. et al., Phys. Plasmas (to be published).