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

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

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

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

Cross-Field Transport in the SOL: Its Relationship to Main Chamber and Divertor Neutral Control in Alcator C-Mod

Evidence for Electromagnetic Fluid Drift Turbulence Controlling the Edge Plasma State in Alcator C-Mod

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

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. Abstract

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

Fluctuation statistics in the scrape-off layer of Alcator C-Mod

Evidence for electromagnetic fluid drift turbulence controlling the edge plasma state in the Alcator C-Mod tokamak

Critical edge gradients and flows with reversed magnetic field in Alcator C-Mod

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

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

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

PSI meeting, Aachen Germany, May 2012

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

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

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

Scaling of divertor heat flux profile widths in DIII-D

Turbulence and flow in the Large Plasma Device

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

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

Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod

A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments

Plasma Science and Fusion Center

Blob sizes and velocities in the Alcator C-Mod scrapeoff

Rapid changes of turbulence propagation direction in the edge of

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

Comments on Particle and Energy Balance in the Edge Plasma of Alcator C-Mod

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

INTERMITTENT TURBULENCE AND COHERENT

1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5.

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

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

Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance

Flow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe

Physics of the detached radiative divertor regime in DIII-D

THE ADVANCED TOKAMAK DIVERTOR

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

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod

Progress in characterization of the H-mode pedestal

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

arxiv: v1 [physics.plasm-ph] 14 Jul 2014

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

Nuclear Fusion Energy Research at AUB Ghassan Antar. Physics Department American University of Beirut

Divertor Requirements and Performance in ITER

3D analysis of impurity transport and radiation for ITER limiter start-up configurations

Some Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

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

Divertor Heat Flux Reduction and Detachment in NSTX

GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK

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

Impact of neutral atoms on plasma turbulence in the tokamak edge region

Development of an experimental profile database for the scrape-off layer

Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod

Predicting the Rotation Profile in ITER

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

Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East

EFDA European Fusion Development Agreement - Close Support Unit - Garching

Volume Recombination and Detachment in JET Divertor Plasmas

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

Transport by Intermittent Convection in the boundary of DIII-D

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma

Characteristics of the H-mode H and Extrapolation to ITER

Fluctuations and transport in the TCV scrape-off layer

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS

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

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France

Highlights from (3D) Modeling of Tokamak Disruptions

Investigation of causes for the discrepancy between the measured and modeled helium emissions using a gas puff imaging diagnostic

Erosion and Confinement of Tungsten in ASDEX Upgrade

High Speed Imaging of Edge Turbulence in NSTX

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

Simulation of Plasma Flow in the DIII-D Tokamak

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Progress in the ITER Physics Basis

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

ICRF Loading Studies on Alcator C-Mod

Edge Plasma Energy and Particle Fluxes in Divertor Tokamaks

Electron temperature barriers in the RFX-mod experiment

Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit. Transport Physics of the Density Limit

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

Edge Impurity Dynamics During an ELM Cycle in DIII D

Pedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability

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

Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak

Experimental results and modelling of ASDEX Upgrade partial detachment

Density Peaking At Low Collisionality on Alcator C-Mod

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

Radial impurity transport in the H mode transport barrier region in Alcator C-Mod

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

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

Divertor physics research on Alcator C-Mod. B. Lipschultz, B. LaBombard, J.L. Terry, C. Boswell, I.H. Hutchinson

Transcription:

Alcator C-Mod Particle Transport in the Alcator C-Mod Scrape-off Layer B. LaBombard, R.L. Boivin, B. Carreras, M. Greenwald, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher, J.L. Terry, S.J. Zweben, Alcator C-Mod Group Presented at the Meeting on Plasma Turbulence and Transport in Edge/SOL Regions 4-5 May, 2, Fairbanks, Alaska

Motivation: Cross-field particle transport (Γ ) in SOL and its dependence on discharge conditions impacts tokamak operation & design Γ determines level of plasma/wall interaction in main-chamber neutral pressures (<=> confinement) impurity sources => impacts divertor design Low Transport High Transport SOL Core Plasma Core Plasma ions neutrals Divertor C-Mod Q: What will be operating regime in a reactor? Heat convection across separatrix and its scaling may play role in tokamak density limit Goals: Characterize and understand Γ : - empirical scalings - underlying turbulence - relationship to tokamak density limit

Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Horizontal Scanning Probe Midplane Dα Fluctuations Behavior Near Discharge Density Limit 6 5 2 4 Vertical Scanning Probe 8 3 6 Divertor Probes

Scrape-off Layer Density Profiles Exhibit a "Two-Exponential" Decay 2 SOL Density Profiles n e /n G =.43 [Ohmic L-Mode] Limiter Shadow (m-3) 9 8 Near SOL n e /n G =.6 5 5 2 25 Separatrix Far SOL Distance into SOL (mm) Near SOL: steep decay, λ n ~ 2 to 8 mm Far SOL: shallow decay, λ n ~ 8 to > mm At low ne, density at limiter edge is less than ~/ of separatrix density Density at limiter edge increases sharply with increasing ne => Always some level of main-chamber (limiter) recycling

Main Chamber Ionization and Fluxes in the Far SOL Are Large Compared to Flows Towards Div./Baffle 23 Main Chamber Ionization (Dα) Ion Flux (D + /s) 22 Flux on Divertor (Div. Probes) Flow Towards Divertor/Baffle (Mach Probe)..2.5 2 ne/n G Recycling in Main Chamber SOL is primarily balance by fluxes onto main-chamber walls Poloidal flows to divertor/baffle are weak Main-Chamber Recycling Regime (MCR) persists over wide parameter range M.V. Umansky, et al. Phys. Plasmas 5, 3373 (998).

A New View of Particle Transport Processes in SOL Old Paradigm: SOL density decays "exponentially" because... plasma drains along field lines towards divertor/baffle SOL Profiles Density Limiter Shadow Ionization FluxTowards Divertor/Baffle Dominates Separatrix SOL drained by parallel flow New Paradigm: SOL density decays "exponentially" because... cross-field transport velocity increases across SOL, maintaining cross-field flux towards wall SOL Profiles Density Limiter Shadow Flux Towards Limiter/Wall Dominates Velocity Ionization Separatrix

Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Fluctuations Edge Thomson Scattering Tangential- Viewing Ly α Array Horizontal Scanning Probe Behavior Near Discharge Density Limit

-5 5 5 2-5 5 5 2-5 5 5 2 (m (m -3 s - ) (m -2 s - ) -3 )2 (m 2 s - ) In MCR Regime, Cross-Field Diffusion Coefficient Profiles (Deff) can be Inferred Directly from Profile Measurements 9 23 22 2 2.. n Sion Γ Deff. -5 5 5 2 Separatrix Distance into SOL (mm) Limiter Shadow - Density n e /n G.43.27.9 - Ionization Source (from Lyα profiles) - Cross-Field Flux Profile - Effective Diffusion Coefficient: Deff = -Γ / n Persistent trend of Deff increasing by ~ or more with distance from separatrix => variation in Deff reflects variation in n Deff increases with discharge density => Γ gets larger, n gets smaller Method benchmarked against UEDGE modeling Deff (χ eff ) increasing seen before: ASDEX, JT-6, JET,...

Magnitude of Deff in Near SOL is Correlated with Collisionality in Near SOL. Regression Analysis of D eff, 2 mm into SOL µte -3.8 n. Ip -.3 BT.8 64 Ohmic L-Mode Datapoints:.8 < ne < 2.5x 2 m -3.6 < Ip <. MA 4 < B T < 6 tesla.4 < ne/n G <.47 (m2 s-)... µ(lei/l) -.7 Multiple Correlation Coefficient =.8 4 Parameter Regression: => Suggests (B T /Ip), q, or L dependence (m2 s-). Multiple Correlation Coefficient =.75.... (m2 s-) Parameter Regression: => Statistics point to (lei/l) as most relevant parameter => Deff correlates with local collisionality: Deff ~ (lei /L) -.7 Trend: ne/n G => lei/l => Deff near sep.

5 5 2 5 5 2 Cross-Field Heat Convection to Limiter/Wall Competes with Parallel Conduction Losses to Divertor at Moderate ne/n G Finite Te on open field lines => power conducted to divertor: Qdiv T 7/2 /L δρ' ρ Cross-field particle fluxes (Γ ) => power convected: Qconv ~ 5 Te Γ A sep 5 Electron Temperature (ev). Power Through Flux Surface ρ (MW)... ne/n G =.9 Qdiv ne/n G =.9 ne/n G =.43 ne/n G =.43 Qconv Qconv Qdiv 5 5 2 ρ (mm) Limiter Distance into SOL Shadow Qconv > Qdiv only in far sol Qconv > Qdiv over entire SOL At low density, heat losses in Near SOL are dominated by parallel conduction to Divertor At moderate density, cross-field heat convection to Limiter/Wall exceeds conduction losses to Divertor/Baffle over entire SOL

Cross-Field Convection Increases with ne/n G, Affecting SOL Power Balance (MW)..8.6.4 Power into SOL [Pin - Prad] Power Conducted to Divertor [Qdiv ] Power Convected to Main-Chamber Limiter.2 Power Convected Across Sep. [Qconv ]..2.3.4.5 n e /n G Outer Divertor Detached At low density, parallel conduction to Divertor dominates SOL power balance At moderate density, cross-field heat convection to Limiter/Wall becomes important => Cross-field convection losses to main-chamber wall may precipitate divertor detachment

A New View of Heat Transport Processes in SOL Old Paradigm: (in absence of a "radiating mantle") Parallel e - conduction to divertor dominates heat losses in Near SOL region Te at separatrix (Tsep) is a weak function of λ T e and SOL power (P sol): Psol Tsep (Psol / λ T e )2/7 Modified Paradigm: Parallel e - conduction and cross-field heat convection contribute to heat losses in Near SOL region (CX is typically a minor player) Psol At low collisionality, parallel conduction regulates Tsep: Tsep (Psol / λ T e )2/7 At high collisionality, heat convection becomes large, Tsep is reduced and is no longer "regulated" by this law!

Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Limiter-Shadow Particle Flux Probe Horizontal Scanning Probe Fluctuations Turbulence Imaging Behavior Near Discharge Density Limit Divertor Probe Triplet

Midplane and Divertor Probe Geometry Midplane Probe 3.8mm Flux Surface Probe Body West North South East Axis of Pyramid Close-up View of Probe Elements Along Axis of Pyramid B-field Direction Four Langmuir Probe Elements:.5 mm dia. tungsten wires, cut to match pyramidal surface Divertor Probe Triplet P P P2 Normal View.5 o 6.6mm B-field Direction 3mm dia. Grazing view Normal view probe triplet B-field Direction P P P2 Grazing View

..5 Time (milliseconds)..5..5 Time (milliseconds)..5..5 Time (milliseconds)..5..5 Time (milliseconds)..5 2 2 2 2 2 Fluctuations Exhibit Different Character in Near and Far SOL Regions ( 2 m -3 ). Near SOL SOL Density Profile Far SOL.2 5 5 2 Distance into SOL (mm) Isat/<Isat> "Snapshots" τ ac ~.2µs 2.2µs 5.5µs 3µs µs..5..5 Time (ms) Limiter Shadow 25 Auto-Correlation Functions Isat/<Isat> (µs) Near SOL (steep n profile): -> moderate amplitude, "random" fluctuations Far SOL (flatter n profile): -> large amplitude, intermittent Isat "bursts" => Consistent with Deff with distance into SOL

..5 Time (milliseconds)..5..5 Time (milliseconds)..5..5 Time (milliseconds)..5..5 Time (milliseconds)..5 - - - - - Fluctuations Exhibit Different Character in Near and Far SOL Regions (ev) 6 4 2 Near SOL SOL Te Profile Far SOL 5 5 2 Distance into SOL (mm) (Vf-<Vf>)/Te "Snapshots" τ ac ~.5µs 3 µs 5 µs 3µs 23µs..5..5 Time (ms) Limiter Shadow 25 Auto-Correlation Functions Vf (µs) Near SOL (steep Te profile): -> moderate amplitude, "random" fluctuations Far SOL (flatter Te profile): -> large amplitude, intermittent Vf "bursts" => Consistent with Deff with distance into SOL

Fluctuation PDFs: ~Gaussian Near Sep., Increasingly Skewed with Distance Into SOL.6.4.2 ( 2 m -3 ) (ev)..2 6 4 2 Near SOL SOL Profiles Density Electron Temperature Far SOL 5 5 2 Distance into SOL (mm) Near SOL (steep Te & n profiles): PDFs have ~Gaussian statistics Limiter Shadow Probability Distribution Functions Floating Potential Skewness: -.9 -.8 -.38 -.77 -.34 Flatness: 2.63 2.55 2.77 3.8 6.95 Ion Current Skewness: -.5.35.483.7 2.4. -4-2 2 4-4 -2 2 4 (Vf-<Vf>)/σ V f (Isat-<Isat>)/σ I sat Far SOL (flatter Te & n profile): Isat PDF has positive tail, Vf negative tail => Consistent with n and Te 'blobs' in Far SOL 25 Flatness: 3.6 3.36 2.95 4.22 2.5

2-D Turbulence Imaging: Intermittent, ~ cm Scale "Blobs" of Emission Extend into Far SOL Near SOL Separatrix Density Far SOL Limiter Shadow Turbulence Imaging: 2-D Images of Da emission, looking along field lines at a "plume" from D2 gas nozzle ~ mm spatial resolution 2 ms exposure times 7 ms between exposures 2 cm ~ cm scale blobs intermittently occupy Far SOL zone, and extend to Limiter Shadow Intermittent "Blobs" (2-D imaging) and "Bursts" (probes) are consistent with large density and temperature (?) perturbations rapidly transporting particles and energy to Limiter/Walls

787.2 787.4 787.6 787.8 msec 788. 788.2 788.4 787.2 787.4 787.6 787.8 msec 788. 788.2 788.4 787.2 787.4 787.6 787.8 msec 788. 788.2 788.4 Isat < Isat > Vf Vf2 ~ Γ < n > Time-History of Fluctuation-Driven Flux Shows Large-Amplitude, Bursty Behavior 3. 2... -2-4 -6-8 -2-4 -6-8 4 2-2 -4 [V] [V] ~ ~ Data from Midplane Probe, 7 mm outside LCFS ~ Particle flux estimate neglects T e ne Velocity [m s - ].2.4.6.8..2 Time [ms] Time-averaged transport velocity: < Γ > < n > ~ 2 m s- Bursts in transport velocity exceed 2 m s - ~ What is influence of T e on these estimates?

~~ <ne> -Derived Cross-Field Flux Shows Similar Trend with as Particle Balance-Derived Flux ne Mean Flux ( 2 m -2 s - ) Estimates of Cross-Field Particle Fluxes (Γ) 7 mm Outside the Separatrix 2 5 5 ~ ~ <ne> (midplane), divided by 8 Particle Balance.5..5 2. 2.5 3. Line-averaged density( 2 m -3 ) ~ ~ ~ <ne> - inferred Γ does not account for possible T e Γ from both methods show similar trend, nonlinearly increasing with ne ~ ~ Magnitude of Γ inferred from Midplane Probe <ne> is a factor of ~8 times larger than that derived from particle balance

PDF of Fluctuation-Driven Particle Flux Exhibits Power-Law Tail, Independent of ne Probability * <Flux> Probability * <Flux> Γ Inferred from Midplane Probe, ~7 mm outside LCFS - -2-3 -4-5 -2-3 -4-5 ne:.8.6.45.3.87-2 3 4 5 6 Flux/<Flux> ne:.8.6.45.3.87 Flux/<Flux> Similar P(Γ ) for all densities => change in <Γ > not associated with change in P(Γ ) Always has SOC-Like behavior: Positive Γ events with Γ greater than 4.6 <Γ > account for 5% of total particle transport. These events happen ~5% of time. Analysis by B. A. Carreras, V. E. Lynch, submitted to PoP.

Fluctuations at Fixed Location in Far SOL Depend on ne/n G Floating Potential Auto-Power Spectra Midplane Probe - -2-3 - -2-3 n e /n G =.4 n e /n G =.22 n e /n G =.3 - f Location maps to 5-8 mm outside LCFS Divertor Probe -2 f 578:Nebar=.87 573:Nebar=.3 579:Nebar=.8-4 -5 2 3 Location maps to 9 mm outside LCFS 4 Hz Breakpoint frequency in Vf power spectra evolve similarly at midplane or divertor locations 5 Different high frequency roll-off 6

Long Time-Range Correlations of Plasma Fluctuations Increase with ne 4 Divertor Probe Data R/S 3 2 - H = H =.5 mesoscale range High density Low density 2 3 4 5 Time lag (µs) Rescaled adjusted range statistic (R/S) indicates increase in long range correlation with ne H.75.7.65.6 999 2 Similar increase in H seen on Midplane and Divertor probes.55 Midplane Divertor.5.8.2.4.6.8 2 Line-averaged density( 2 m -3 ) Analysis by B. A. Carreras, V. E. Lynch, submitted to PoP.

Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Limiter-Shadow Particle Flux Probe Horizontal Scanning Probe Fluctuations Behavior Near Discharge Density Limit

..2.4 seconds.6.8...2.4 seconds.6.8. (MA) Collisionality at the Separatrix and Heat Convection to Limiter/Wall Increases as Discharge Density Limit is Approached (MW) Diverted Discharge with Ramping ne/n G. 5 Plasma Current.5 2..5 Input Power ne/n G Line Averaged Density Radiated Power λei/l....2.4.6.8. (seconds) Horizontal Scanning Probe records profiles at three times 4 3 2 ( 2 m -3 ).8.4 Heat Convection to Limiter/Wall based on Limiter Particle Flux Probe λei/l, mm into SOL As density limit is approached: λei/l near separatrix drops dramatically Radiation and Convection to Limiter/Wall are comparable and mostly account for input power Near density limit: Radiation + Convection to Walls ~ Input Power

-2 2 4 6 8 2 2 4 6 8 2-2 2 4 6 8 2 Near Density Limit: Large Amplitude, Long- Correlation Time Fluctuations Envelop Entire SOL and Cross Separatrix n / n G at separatrix does not increase!.4. SOL Profiles Density / n G ne/n G.82.4.34 (ev) 6 4 2-2 Electron Temperature (µs) -2 Auto-Correlation Times (Vf data).3. -2 2 4 6 8 2 Separatrix Distance into SOL (mm) RMS Isat/<Isat> Near density limit: SOL n & Te profiles become flat, Tsep low ~ 25 ev! Fluctuations characteristic of "Far SOL" now occur everywhere, even across the separatrix => Consistent with large Convection Losses

Summary C-Mod SOL Core Plasma Divertor SOL density profiles exhibit a "twoexponential" decay: Near and Far SOL Yet, Main-chamber plasma exhausts primarily onto Limiter/Wall surfaces! - Why? - => New Particle Transport Paradigm: Density "decays exponentially" because... cross-field transport (Deff ) increases rapidly with distance into SOL... not because parallel flows "drain" SOL plasma Particle (Deff) and heat convection near separatrix increases with collisionality: Deff ~ (λei /L) -.7 => Heat Transport Paradigm Modified: At moderate collisionality (ne/n G ~.5), crossfield heat convection exceeds conduction losses Tsep no longer regulated by "conduction law": Tsep (Psol / λ T e )2/7

Summary (page 2) Fluctuation behavior supports picture of particle & energy transport increasing with distance into SOL Near SOL: (steep density profile) low amplitude "random" fluctuations Far SOL: (flat density profile) large amplitude intermittent "bursts" in Isat and ~ cm "blobs" in Dα, extending into Limiter Shadow ~ ~ <ne> -derived cross-field flux (Γ) supports results inferred from particle balance: Γ similarly increases with ne Γ is factor of ~8 times larger than particle balance => supporting MCR conclusion Far SOL turbulence has some SOC-like characteristics (~generic to edge plasmas) PDF(Γ) has power-law tail (independent of ne ) Long-range time correlations are increasingly seen as ne is increased

Summary (page 3) => New Insight on Density Limit Physics: As density limit is approached, λei/l near separatrix drops and transport across the SOL increases dramatically Heat Convection to Limiter/Wall becomes large fraction of input power "Bursty" fluctuations (large transport) occur over entire SOL and begins to attack plasma on closed flux surfaces ~ at limit: Radiation + Convection to Wall ~ Input Power Rapid increase of Heat Convection as edge plasma cools may play role in thermal instability leading to disruption