Varia%ons in Edge and SOL Turbulence in NSTX

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

Blob sizes and velocities in the Alcator C-Mod scrapeoff

High Speed Imaging of Edge Turbulence in NSTX

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

Modeling neutral-plasma interactions in scrape-off layer (SOLT) simulations*

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

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod

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

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

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

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod

Divertor Heat Flux Reduction and Detachment in NSTX

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

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

SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS

Lower Hybrid Wave Induced Rotation on Alcator C-Mod* Ron Parker, Yuri Podpaly, John Rice, Andréa Schmidt

Development of a New Gas Puff Imaging Diagnostic on the HL-2A Tokamak

Invited Review Article: Gas Puff Imaging Diagnostics of Edge Plasma Turbulence in Magnetic Fusion Devices. X Science LLC, Plainsboro, NJ 08536, USA

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

Plasma Science and Fusion Center

Non-Solenoidal Plasma Startup in

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer

Results From Initial Snowflake Divertor Physics Studies on DIII-D

Supported by. Role of plasma edge in global stability and control*

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

Experimental investigation of the parallel structure of fluctuations in the scrape-off layer of Alcator C-Mod

NSTX. Electron gyro-scale fluctuations in NSTX plasmas. David Smith, PPPL. Supported by

Scaling of divertor heat flux profile widths in DIII-D

Particle and Energy Transport in the SOL of DIII-D and NSTX

L-mode filament characteristics on MAST as a function of plasma current measured using visible imaging

Characteristics of the H-mode H and Extrapolation to ITER

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

Investigations of pedestal turbulence and ELM bursts in NSTX H-mode plasmas

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

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

D. Smith, R. Fonck, G. McKee, D. Thompson, and I. Uzun-Kaymak

Predicting the Rotation Profile in ITER

Supported by. The dependence of H-mode energy confinement and transport on collisionality in NSTX

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

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

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

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

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

UCLA. Broadband Magnetic and Density Fluctuation Evolution Prior to First ELM in DIII-D Edge Pedestal. Presented by G. Wang a, In collaboration with

Scaling of divertor heat flux profile widths in DIII-D

3-D Random Reconnection Model of the Sawtooth Crash

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta

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

Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields

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

Convective transport by intermittent blob-filaments: comparison of theory and experiment

Triggering Mechanisms for Transport Barriers

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

Initial Investigations of H-mode Edge Dynamics in the PEGASUS Toroidal Experiment

G. Rewoldt, W.X. Wang, M. Bell, S. Kaye, W. Solomon, R. Nazikian, and W.M. Tang Princeton Plasma Physics Lab 1

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

Disruption dynamics in NSTX. long-pulse discharges. Presented by J.E. Menard, PPPL. for the NSTX Research Team

Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U *

Phase ramping and modulation of reflectometer signals

Rapid changes of turbulence propagation direction in the edge of

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

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

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

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation

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

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU

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

Physics of the detached radiative divertor regime in DIII-D

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

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS

Edge Impurity Dynamics During an ELM Cycle in DIII D

Spa$al structure of low- frequency plasma fluctua$ons in a laboratory dipole experiment

MHD-Induced Alpha Particle Loss in TFTR. S.J. Zweben, D.S. Darrow, E.D. Fredrickson, G. Taylor, S. von Goeler, R.B. White

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

Resistive Wall Mode Control in DIII-D

ABSTRACT, POSTER LP1 12 THURSDAY 11/7/2001, APS DPP CONFERENCE, LONG BEACH. Recent Results from the Quiescent Double Barrier Regime on DIII-D

Penetration of filamentary structures into the divertor region of spherical tokamaks

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Magnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria

ELMs and Constraints on the H-Mode Pedestal:

Blob motion and control. simple magnetized plasmas

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

Thin Faraday foil collectors as a lost ion diagnostic

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

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

New bootstrap current formula valid for steep edge pedestal, and its implication to pedestal stability

Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas *

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL

Low-collisionality density-peaking in GYRO simulations of C-Mod plasmas

David R. Smith UW-Madison

H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod

Study of chirping Toroidicity-induced Alfvén Eigenmodes in the National Spherical Torus Experiment

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

DT Fusion Power Production in ELM-free H-modes in JET

Behavior of Compact Toroid Injected into the External Magnetic Field

Transcription:

Varia%ons in Edge and SOL Turbulence in NSTX S.J. Zweben 1*, W.M. Davis 1, S.M. Kaye 1, J.R. Myra 2, R.E. Bell 1, B.P LeBlanc 1, R.J. Maqueda 1**, T. Munsat 3, S.A. Sabbagh 4, Y. Sechrest 3, D.P. Stotler 1, and the NSTX Team 1 Princeton Plasma Physics Laboratory, Princeton NJ 08540 USA 2 Lodestar Research CorporaTon, Boulder, CO, USA 3 Department of Physics, Univ. of Colorado, Boulder CO 80309 USA 4 Dept. of Appl. Phys. and Appl. Math, Columbia Univ., New York, NY10026 USA *szweben@pppl.gov **presently at X Science LLC, Plainsboro, NJ 08543 USA This work was supported by USDOE Contract #DE- AC02-09CH11466 TTF meetng, Salem MA, Thurs. Apr. 30, 2015, poster #12 1

Abstract This poster describes the range of variatons in edge and SOL turbulence observed using a gas puff imaging (GPI) diagnostc in NSTX discharges. The database consists of 140 shots including Ohmic, L- mode, and H- mode plasmas measured during steady- state conditons (e.g. without ELMs). Turbulence quanttes were evaluated using both cross- correlaton analysis and blob tracking. RelaTve fluctuaton levels varied from di/i~15-100%, correlaton Tmes were t auto ~15-40 µsec, correlaton lengths were L pol ~ L rad ~5-10 cm, and turbulence velocites were V pol ~2±1 km/sec and V rad ~0.5±0.5 km/sec outward. These variatons were evaluated with respect to both the global and local edge plasma parameters, and compared with simplified theoretcal models. 2

Gas Puff Imaging (GPI) Diagnos%c on NSTX D 2 gas puffed from GPI manifold on outer wall above midplane Dα light emission from gas puff viewed from along local B field FluctuaTons in Dα light emission interpreted as edge turbulence GPI gas puffer Dα emission from puff B field RF limiter GPI op%cal viewport 3

Time Dependence of GPI Signals GPI gas puffed once during shot and seen by local Dα emission Time of analysis for this database is ±5 msec around GPI peak plasma current (ka) NBI (MW) GPI Dα (rel.) average density (10 13 cm - 3 ) GPI gas puff %me of analysis 4

Typical Camera Images from GPI in NSTX Image data first normalized by average of images over 1 msec PosiTve excursions 1.5 normalized signal are tracked as blobs 5

Selec%on of Shots for the GPI Database Taken from 17 different XPs in 2010, H- mode, Ohmic, and L- mode All diverted deuterium plasmas, almost all (93%) lower- single- null Time of interest during steady- state with no transient events, i.e. no large ELMs, MHD, power varia4ons, or L- H transi4ons B field line angle suitable for GPI (i.e. I p /B t = 0.2±0.05 MA/kG) GPI data taken at fastest possible rate of 400,000 frames/sec Outer midplane separatrix at least 3 cm inside GPI field of view 6

NSTX GPI Database from 2010 Run Overall database Number of shots 140 H- mode 93 Ohmic 33 L- mode 14 Plasma current: I p =0.65-1.15 MA Toroidal field: B t =3.5-5.5 kg safety factor: q 95 = 5.8-12.8 ElongaTon k=1.8-2.5 Stored energy: W mhd =26-306 kj Average density: n e =1.3-7.0x10 13 cm - 3 NBI heatng: P nb = 0-6 MW RF heatng: P rf = 0-1.4 MW Outer gap: 2.8-15.7 cm Lithium: 0-370 mg/shot Sample plasmas used for profiles H- mode Ohmic shot range 140389-395 141746-756 Tme (sec) 0.532 0.215 I p (ka) 830 830 B t (kg) 4.9 3.6 W mhd (kj) 220 32 n e (10 13 cm - 3 ) 5.2 1.6 P nb (MW) 4.0 0 T e (0) (ev) 920 530 n e (0) (10 13 cm - 3 ) 5.6 2.3 T e (a) (ev) 29±17 13±6 n e (a) (10 13 cm - 3 ) 0.92±0.54 0.37±0.23 T e @ - 2 cm (ev) 134±53 23±4 n e @ - 2 cm (/10 13 ) 2.1±0.47 0.47±0.17 7

Sample Edge Profiles in NSTX Te and ne profiles from Thomson scasering (7 shots each) GPI profiles from average Dα over Tme near peak Tme 8

Turbulence and Blob Data Analysis Image data first normalized by average of images over 1 msec Turbulence analysis uses standard cross- correlaton methods, averaging results over ±5 msec around peak of GPI signal Blob analysis tracks structures with height 1.5 x average height at that spatal positon, averaging over ±5 msec as above Results binned near - 2 cm, 0 cm, +2 cm, +4 cm from separatrix SomeTmes shots are segregated into H- mode, Ohmic, L- mode 9

Sample of Database Results and Analysis Turbulence amplitudes - δi/i Blob amplitudes N blob and A blob Turbulence size scales L pol and L rad Blob size scales blob L pol and blob L rad Poloidal turbulence and blob velocity V pol and blob V pol Radial turbulence and blob velocity V rad and blob V rad Cross- correlaton and regression analysis τ auto and blob lifetme whole database can be found at: hsp://w3.pppl.gov/~szweben/nstx2013/nstx2013.html 10

Turbulence Amplitudes (a) (b) (c) (d) (e) (f) 11

(a) Blob Amplitudes (b) (c) (d) (e) (f) 12

Turbulence Length Scales (a) (b) (c) (d) (e) (f) 13

Blob Length Scales (a) (b) (c) (d) (e) (f) 14

Turbulence and Blob Poloidal Velocity (a) (b) (c) (d) (e) (f) 15

Turbulence and Blob Radial Velocity (a) (b) (c) (d) (e) (f) 16

Correla%on Times and Blob Life%mes Turbulence autocorrelaton Tme increases with minor radius AutocorrelaTon Tme τ auto ~ L pol /V pol, approx. frozen flow Total blob lifetme in GPI viewing region ~ τ auto (a) (b) (c) 17

Turbulence Cross- Correla%on Coefficients showing only cases with 50% cross- correlaton coefficient 18

Power Law Exponents for Turbulence Single parameter (pair wise) exponents MulTple parameter (regression) exponents 19

Summary of Some Turbulence Varia%ons difficult to briefly summarize all the observed varia4ons RelaTve fluctuaton level increases with radius, but decreases with density, total stored energy, and edge T e and grad P e Poloidal and radial turbulence scale lengths are roughly constant vs. radius and within a factor- of- two of each other Poloidal velocity IDD except for EDD in Ohmic inside separatrix, and independent of density, stored energy, and P nb Radial turbulence speed outward at 0-1 km/sec Blob propertes generally similar to turbulence propertes 20

Turbulence Amplitude vs. Theory Expect for saturaton by wave breaking: δn/n ~ 1/k rad L n Expect for saturaton of interchange modes: δn/n ~ V rad ω/l n Assume k rad ~ 2/L rad, ω 2/τ auto, δn/n ~ δi/i for GPI at ρ= - 2 cm Measured δi/i are below these limits, especially for H- mode 21

Turbulence Length Scales vs. Theory Driy wave turbulence models have typically k pol ρ s ~ 0.3 Interchange turbulence typically has L rad ~ L p(ressure) Measured size scales are ~3-5 Tmes larger than these 22

Turbulence Poloidal Velocity vs. Theory Expect driy waves have V pol = ± V driy = ± c s ρ s /L n in rest frame At ρ = - 2 cm, V pol (OH) is close to V d,e, but V pol (H) ~ (1/3) V d,i Ion V pol in H- mode may be due to: 1) shiy from e - to i + driy waves 2) increased outward E rad 3) NBI- induced toroidal rotaton V pol (NBI) ~ (B p /B t ) V tor V pol (NBI) ~ - 1-10 km/sec (?) 23

Blob Radial Velocity vs. Theory Sheath- limited radial blob velocity: V sl = c s (L II /R) (ρ s /δ b ) 2 (δn/n) InerTal regime radial blob velocity: V in = c s (δ b /R) 1/2 (δn/n) 1/2 Assume T e from ρ= 0 cm, δ b ~ L pol /2, R=150 cm, δn/n ~ δi/i Measured blob V rad @ ρ= +2 cm lies between V sl and V in 24

Summary of Comparisons with Theory Amplitudes of turbulence δi/i at ρ = - 2 cm in H- mode are lower than expected from simple theoretcal estmates Poloidal turbulence size scale L pol at ρ = - 2 cm is in between simple driy- wave and interchange scale lengths Poloidal speed of turbulence V pol at ρ = - 2 cm is about x3 lower than diamagnetc driy velocites Radial blob speed V rad from GPI at ρ = +2 cm is in between estmates based on sheath limited and inertal range models => partal consistency with driy- wave and interchange estmates see Myra poster P13 for further theory analysis of database 25

Some New or Surprising Results No significant increase in the poloidal turbulence velocity with increased NBI power over P nb ~2-6 MW in H- mode plasmas The local radial correlaton lengths just inside the separatrix in H- mode plasmas were ~2-5 Tmes larger than the local density gradient scale, which seems inconsistent with driy wave theory There was relatvely lisle variaton of the turbulence or blob propertes with respect to plasma current or toroidal field Although not new, there was a surprisingly clear reversal in poloidal turbulence velocity with radius in Ohmic plasmas Near absence of blobs inside the separatrix for H- mode plasmas 26

Overall Summary and Conclusions Edge and SOL fluctuaton levels large in all shots in database, δi/i 15%- 100% Turbulence correlaton analysis and blob tracking analysis give similar results in almost all cases Could not find clear empirical scalings of turbulence variatons with respect to global plasma or edge parameters ParTal consistency with driy wave / interchange / blob models Conclusion is that edge turbulence is not well understood 27