Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

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

Plasma Science and Fusion Center

Scalings of nonlinearity in the edge plasma and its connection to transition thresholds

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

IF2011 Pedestal/JRT Summary. J.W. Hughes 21 Jan 2011

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

C-Mod Transport Program

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

Blob sizes and velocities in the Alcator C-Mod scrapeoff

Predicting the Rotation Profile in ITER

Understanding Edge Harmonic Oscillation Physics Using NIMROD

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

Influence of Beta, Shape and Rotation on the H-mode Pedestal Height

ELMs on C-Mod. J.W. Hughes for the Alcator C-Mod team. C-Mod/NSTX Pedestal Workshop Princeton, NJ September 7 8, 2010

Turbulence and Transport The Secrets of Magnetic Confinement

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

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

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

Characteristics of the H-mode H and Extrapolation to ITER

Progress of Confinement Physics Study in Compact Helical System

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

Rapid changes of turbulence propagation direction in the edge of

On the physics of shear flows in 3D geometry

ELMs and Constraints on the H-Mode Pedestal:

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

Pedestals and transitions in I-mode and comparison to H-mode

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

Theory Work in Support of C-Mod

Correlation Between Plasma Rotation and Electron Temperature Gradient Scale Length in LOC/SOC Transition at Alcator C-Mod

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

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

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

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

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

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

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

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

Corresponding Authors s address:

EX/4-6Rb Electrostatic fluctuation and fluctuation-induced particle flux during formation of the edge transport barrier in the JFT-2M tokamak

I-mode and H-mode plasmas at high magnetic field and pressure on Alcator C-Mod

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

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

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

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

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

ITB Transport Studies in Alcator C-Mod. Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co

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

Progress in characterization of the H-mode pedestal

Neoclassical transport

Role of Low-Order Rational Surfaces in Transport Barrier Formation on the Large Helical Device

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

Edge Impurity Dynamics During an ELM Cycle in DIII D

Correlation between the edge and the internal transport barriers in JT-60U

Scaling of divertor heat flux profile widths in DIII-D

Current Drive Experiments in the HIT-II Spherical Tokamak

Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT-2 Tokamak

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center

This is a repository copy of Radial localization of edge modes in Alcator C-Mod pedestals using optical diagnostics.

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

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

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Confinement of toroidal non-neutral plasma in Proto-RT

H-mode in Helical Devices

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

LITHIUM DIAGNOSTIC BEAM DEVELOPMENT FOR FUSION PLASMA MEASUREMENTS PhD thesis GÁBOR ANDA. Thesis Supervisor: DR. SÁNDOR ZOLETNIK MTA KFKI RMKI

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

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

Reduction of Turbulence via Feedback in a Dipole Confined Plasma. Thomas Max Roberts Applied Physics Applied Mathematics Columbia University

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

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U

Turbulence and flow in the Large Plasma Device

Edge and SOL turbulence on HFS/LFS at ASDEX Upgrade by Microwave Reflectometry

Validation Study of gyrokinetic simulation (GYRO) near the edge in Alcator C-Mod ohmic discharges

EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY*

Triggering Mechanisms for Transport Barriers

DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS

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

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

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

INTERMITTENT TURBULENCE AND COHERENT

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

Erosion and Confinement of Tungsten in ASDEX Upgrade

Edge Momentum Transport by Neutrals

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

Divertor Heat Flux Reduction and Detachment in NSTX

0 Magnetically Confined Plasma

ICRF Mode Conversion Flow Drive on the Alcator C Mod Tokamak

Size Scaling and Nondiffusive Features of Electron Heat Transport in Multi-Scale Turbulence

Electron temperature barriers in the RFX-mod experiment

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Confinement of toroidal non-neutral plasma in Proto-RT

Development of a Lithium Beam Probe and Measurement of Density Pedestal in JT-60U

TURBULENT TRANSPORT THEORY

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1

TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings

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

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

Confinement and Transport Research in Alcator C-Mod

The Levitated Dipole Experiment: Towards Fusion Without Tritium

Overview of Recent Results from Alcator C-Mod including Applications to ITER Scenarios

Transcription:

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak István Cziegler UCSD, Center for Energy Research Center for Momentum Transport and Flow Organization Columbia Seminar Feb 2, 212

OR Edge Fluctuations and You

Tokamak and notations for toroidal geometry R φ z R θ a r R ŸTokamak is a magnetic confinement device Ÿstrong toroidal field confines particles Ÿfield lines bent into torus to prevent losses Ÿnecessary poloidal field provided by toroidal plasma current R - major radius r - minor radius φ -toroidal angle θ - poloidal angle Ÿflux surfaces exist

An operational mode of high confinement was discovered in the 8 s that features reduced turbulence. No first principles theory exists yet to predict the onset and cause of H-mode Empirical work shows that the transition is related to the creation of strongly sheared flows that break apart turbulent eddies Complex self-organization ExB shear mostly present in periphery of plasma; transport barrier and leads to local edge instabilities..edge Localized Modes, ELM which periodically relax the edge gradient--these have a major impact on heat loads on plasma facing mat. Empirical scaling shows that there exist a critical power across boundary of plasma is needed to initiate H-mode Also sensitive to plasma shape and the presence of a divertor and vacuum cleanliness. 14 12 1 8 6 4 2 2. b) n e (1 2 m -3 ) 1..5. 2.5 2. c) T e (kev) 1..5. d) H 98 1..5. 4 e) P 3 RAD (kw) 2 1 L-mode a) Dα ELM crashes.7.8.9 1. 1.1 1.2 Time (s) H-mode

Why aren t we happy with garden variety H-modes? ŸELM ejections already limit the lifetime of plasma facing components ŸReal fusion devices need to be ~1x larger: 1x volume, yet only 1x surface! ŸELMfree H-modes exist with near zero edge turbulence, BUT: P BS n e Te 1/2 bremsstrahlung leads to collapse Ÿenergy and mass (and impurity) transport processes are coupled i n i Z 2 i 2 15 1 5 2.5 2. 1..5. 2. 1..5. 1.2 1..8.6.4.2. 4 3 2 1 a) Dα b) n e (1 2 m -3 ) c) T e d) H 98 (kev) e) P RAD (kw).7.8.9 1. 1.1 1.2 Time (s) ELMfree H-mode

Experimental setup of the new 2D fast Gas-Puff-Imaging diagnostic Side View Ÿ Ÿ gas puff injects neutral D 2, or He sensitive to n e, Te Top View Toroidal view of Outboard Edge limiter Ÿ small toroidal extent (~5cm) allows localization Ÿ 9 channels cover ~ 4.4cm x 4cm nozzle Ÿ views coupled to APD arrays, sampled @ 2MHz Ÿ limiter gas puff

High confinement regimes with enhanced particle transport - EDA H-mode, I-mode Ÿ In recent years both the EDA H-mode and the I-mode have started to be viewed as special high energy confinement regimes Ÿ The QCM plays a significant role in regulating the edge transport and providing a non-explosive way of releasing impurities and relaxing the pedestal profile Ÿ In the I-mode regime the WCM has been implicated as either a contributor to enhanced, essentially L-mode level particle transport or a part of the dynamics leading to the development of an energy transport barrier. S(k θ ν)=s(k θ,ν)/s(ν) Frequency (khz) 3 2 1 EDA H-mode conditional spec -6-4 -2 2 4 6 k θ (cm -1 ) Frequency (khz) 3 2 1 I-mode conditional spec -6-4 -2 2 4 6 k θ (cm -1 )

I-mode has Te and Ti pedestal, no density barrier Edge/Pedestal/SOL Profiles Steep T pedestal (electrons and ions) leads to increased core T, stored energy H-mode has similar T pedestal, but much higher and steeper density pedestal. L-mode like density profile, broad SOL I-mode Access: Unfavorable grad-b drift gives easiest access, largest operational window

New results on the two fluctuations suggest flow shear is important in determining structure δn/n (integrated for full peak) E r (kv/m).4.3.2.1. QCM WCM -.1-2 -1 1 2 Distance from LCFS (cm) 6 4 2-2 -4 separatrix Phase shift across the mode π/4 -π/4 -π/2-3π/4 Σb 2 mod 1 -π.4.5.6.7.8.9 1..5.6.7.8.9 1. 1.1 H 98 H 98 8 6 4 2 QCM Lab frame velocity (km/s) 15 1 5-5 -1-15 WCM.4.6.8 1. 1.2 H 98 Ÿ Both features show clear scaling with the confinement factor - known to scale with the depth of the electric well. Ÿ The QCM develops a stronger and stronger harmonic structure Ÿ The WCM speeds up linearly with the ExB drift -5-4 -3-2 -1 1 Distance from LCFS (cm) The two features are radially localized to the same region where E well exists r according to CXRS The propagation in the opposite directions is further corroborated by the typical onset spectrograms, showing the QCM spin down and the WCM spin up as their respective high confinement regimes develop from an L-mode plasma.