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

Similar documents
Effect of RMPs on the edge turbulence in ohmic and L-mode plasmas

Turbulence and geodesic acoustic mode behavioural studies in ASDEX Upgrade using Doppler Reflectometry

Spatio-temporal investigations on the triggering of pellet induced ELMs

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas

The I-phase and its relation to other phenomena at AUG

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

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

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

Development of a 2D full-wave JE-FDTD Maxwell X-mode code for reflectometry simulation

Microwave Reflectometry in TJ-II

Studies of the Quiescent H-mode regime in ASDEX Upgrade and JET

Long-Range Correlations and Edge Transport Bifurcation in Fusion Plasmas

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET

ITR/P1-19 Tokamak Experiments to Study the Parametric Dependences of Momentum Transport

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

EX/4-2: Active Control of Type-I Edge Localized Modes with n = 1 and n = 2 fields on JET

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

Divertor Power Handling Assessment for Baseline Scenario Operation in JET in Preparation for the ILW

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

Plasma response of magnetic perturbation at the edge: Comparisons between measurements and 3D MHD models

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

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

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

Corresponding Authors s address:

Improved Confinement in JET High b Plasmas with an ITER-Like Wall

Fast Particle Physics on ASDEX Upgrade Interaction of Energetic Particles with Large and Small Scale Instabilities

Phase ramping and modulation of reflectometer signals

Direct measurements of the plasma potential in ELMy H mode. plasma with ball pen probes on ASDEX Upgrade tokamak

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform

Physics of fusion power. Lecture 14: Anomalous transport / ITER

1999 RESEARCH SUMMARY

T. PÜTTERICH et al. 1

Plasma Spectroscopy in ISTTOK

EXD/P3-23. Fluctuations, ELM Filaments and Turbulent Transport in the SOL at the Outer Midplane of ASDEX Upgrade

Progress of Confinement Physics Study in Compact Helical System

Three Dimensional Measurements Of Geodesic Acoustic Mode with Correlation Doppler Reflectometers

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139

Overview of Experimental Results on HL-2A

C-Mod Transport Program

Overview of results from MAST Presented by: Glenn Counsell, for the MAST team

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

EX8/3 22nd IAEA Fusion Energy Conference Geneva

VII. Publication VII IOP Publishing Ltd. By permission.

2D ECE measurements of type-i Edge Localized Modes at ASDEX Upgrade

EX/P3-31. Scalings of Spontaneous Rotation in the JET Tokamak

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

Observation of modes at frequencies above the Alfvén frequency in JET

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

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

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak

Implications of JET-ILW L-H Transition Studies for ITER

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

Progressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.

Triggering Mechanisms for Transport Barriers

Doppler Reflectometry Simulations for ASDEX Upgrade

Overview of EAST Experiments on the Development of High-Performance Steady- State Scenario

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

Predicting the Rotation Profile in ITER

STUDY OF ADVANCED TOKAMAK PERFORMANCE USING THE INTERNATIONAL TOKAMAK PHYSICS ACTIVITY DATABASE

Three dimensional measurements of Geodesic Acoustic Mode with correlation Doppler reflectometers

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

Erosion and Confinement of Tungsten in ASDEX Upgrade

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

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

Plasma turbulence measured by fast sweep reflectometry on TORE SUPRA

Electron Bernstein Wave Heating in the TCV Tokamak

Fusion Research at the ASDEX Upgrade Tokamak Experiences with Tungsten Plasma Facing Components

Retarding field energy analyzers for the ion temperature measurements in the SOL plasmas of the tokamak ISTTOK and the TJ-II stellarator

Radiative type-iii ELMy H-mode in all-tungsten ASDEX Upgrade

Influence of Impurity Seeding on ELM Behaviour and Edge Pedestal in ELMy H-Mode Discharges

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

Non-linear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade

Be tile power handling and main wall protection

Characterization of the Perpendicular Rotation Velocity of the Turbulence by Reflectometry in the Stellarator TJ-II

Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany

Scaling of divertor heat flux profile widths in DIII-D

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

Discrepancy between modelled and measured radial electric fields in the scrape-off layer of divertor tokamaks: a challenge for 2D fluid codes?

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

Erosion and Confinement of Tungsten in ASDEX Upgrade

1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator

Plasma turbulence measured with fast frequency swept reflectometry in JET H mode plasmas

C-MOD PAC FEBRUARY, 2005 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

Power Exhaust on JET: An Overview of Dedicated Experiments

Effect of ECRH Regime on Characteristics of Short-Wave Turbulence in Plasma of the L-2M Stellarator

Turbulence and transport reduction with innovative plasma shapes in TCV - correlation ECE measurements and gyrokinetic simulations

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

Edge Plasma Energy and Particle Fluxes in Divertor Tokamaks

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

Active Control of Type-I Edge Localized Modes with n=1 and n=2 fields on JET

Tungsten: An option for divertor and main chamber PFCs in future fusion devices

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

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

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

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

MHD Induced Fast-Ion Losses in ASDEX Upgrade

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

Edge Momentum Transport by Neutrals

Recent Progress in Understanding the Processes Underlying the Triggering of and Energy Loss Associated with Type I ELMs

Transcription:

Edge and SOL turbulence on HFS/LFS at ASDEX Upgrade by Microwave Reflectometry V.E. Nikolaeva1,2, M. E. Manso1, L. Guimarais1, U.Stroth3, G. D. Conway3, C. Silva1, and the ASDEX Upgrade team Associação Euratom/IST, Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade Técnica de Lisboa, 1049-001 Lisboa, Portugal 2Technische Universität München, James-Franck-Str. 1, D-85748 Garching, Germany 3 Max Planck Institut für Plasmaphysik, EURATOM Association, Garching, Germany 1

Outlook Begin at the beginning," the King said, very gravely, "and go on till you come to the end: then stop. Lewis Carroll, Alice in Wonderland Motivation Experimental set up Methodology HFS/LFS SOL/edge density fluctuations in L-mode Radial profile dn/n RMP effect Asymmetry dn/n in USN, DN, LSN Triangularity/power effect at LFS Summary

Turbulence is widely spread phenomena Hi-C, NASA Photo by Marc Mawson

Why do we investigate turbulence?

Why do we investigate turbulence?

Why do we investigate turbulence in fusion? Motivation Plasma turbulence greatly enhances energy and particles transport across magnetic field lines Anomalous transport processes degrade plasma confinement Investigation of turbulence properties is important to improve efficiency/reliability of a fusion reactor

Principles of reflectometry diagnostic O-Mode: Ewave B0: solely depend on ne 2 1 nc e F c= 2 π ϵ0 m e A(t)cos[2πF0 + φ(t)] to get φ(t) Hilbert transform relation between phase φ(t) and the density fluctuation level δne/ne determined from (O mode): 1D model by C.Fanack: 2/3 1/3 Large wavenumbers 2ka< kf < 2k0: k A =0.63 k 0 L δn 0 Δϕmax k f / k 0 = ncr π 2 L/ λ 0 1/ 2 ( ) Ln = nc ne

ASDEX Upgrade tokamak (Axially Symmetric Divertor EXperiment) major radius (R) 1.65 m minor radius (a) 0.5 m 1.6 ma max plasma current (Ip) max toroidal magnetic field (Bt) 3.1 T max pulse duration max electron density (ne) 10 s 1020 m-3

ASDEX Upgrade tokamak (Axially Symmetric Divertor EXperiment) major radius (R) 1.65 m minor radius (a) 0.5 m 1.6 ma max plasma current (Ip) max toroidal magnetic field (Bt) 3.1 T max pulse duration max electron density (ne) 10 s 1020 m-3

HFS&LFS FMCW reflectometer Density [x1019m-3] V 3.0-7.0 Q 1.5-3.0 Ka 0.8-1.5 K 0.3-0.8 Fluctuation Data: 8s @2MHz LFS Z=0.14 HFS Z=0.07

HFS/LFS radial profile of density fluctuations ne = 0.71*1019 m-3 SOL decrease of δn/n inside of LCFS LFS HFS Thesis of E. Viezzer, 2012

RMP effect RMP effect on HFS/LFS on HFS/LFS SOL density SOL density fluctuation fluctuation ne = 0.36*1019 m-3 SOL without RMP with RMP HFS Ref without RMP with RMP Magnetics LFS Ref HFS Ref RMP

Turbulence asymmetries HFS/LFS in USN, DN, LSN USN LSN USN Ka ne=1*1019 m-3 edge LFS HFS LFS K ne=0.4*1019 m-3 SOL HFS

Strong poloidal asymmetry in fluctuation amplitudes measured with LFS/HFS reflectometer LSN DN RMP USN RMP USN DN LSN USN LFS HFS LFS DN LFS HFS HFS LSN Edge stronger asymmetry in USN, not such a strong asymmetry like at SOL SOL - strongest asymmetry in DN; USN DN LSN USN dn/n higher both at LFS/HFS LSN DN RMP USN RMP not clear DN, dn/n high at HFS

Turbulencechanges changeswith withtriangularity, triangularity,lfs LFS Turbulence H-mode, ELM suppression density shoulder steep region density shoulder steep region Changes are observed only at low power and at the shoulder region where turbulence seems to increase with δ (from #30728 to #30718)

Turbulencechanges changeswith withnbi NBIpower, power,lfs LFS Turbulence density shoulder density shoulder steep region steep region Changes are observed mainly at the shoulder region, in case of medium δ effect is more pronounced, turbulence decreases with increase of NBI power

Summary HFS/LFS SOL/edge assymmetries Drop of density fluctuations inside close to LCFS Effect of RMP coils is mainly pronounced on HFS SOL HFS/LFS SOL/edge density fluctuations asymmetry observed in L-mode in USN, DN, LSN configurations Triangularity and power effect, LFS At higher power effect of triangularity on density turbulence from separatrix to pedestal area is not pronounced At low power effect of triangularity is seen at density profile shoulder, turbulence is higher for higher triangularity

Thank you for your attention!

Experimental set up, HFS/LFS reflectometers O-Mode: Ewave B0: Independent of magnetic field. WKB approximation. Multi-channel reflectometer diagnostics Hopping LFS reflectometer RFL LFS 2 channels [FLQ, FLV] FF or hopping density fluctuation measurements heterodyne: in-phase & quadrature (IQ) detector: I(t) = A(t)cos(φ(t)) & Q(t) = A(t)sin(φ(t)) separation phase φ(t) & amplitude A(t) fluctuations FMCW LFS&HFS reflectometer RTR LFS: 5 channels [K, Ka, Q, V, W] HFS: 4 channels [K, Ka, Q, V] swept frequency profiles measurements or FF density fluctuation measurements homodyne: single ended detector A(t)cos[2πF0 + φ(t)] F0 microwave source frequency toroidal section of AUG tokamak