Mechanisms of intrinsic toroidal rotation tested against ASDEX Upgrade observations

Similar documents
Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod

Gyrokinetic simulations including the centrifugal force in a strongly rotating tokamak plasma

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

TURBULENT TRANSPORT THEORY

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

Intrinsic rotation due to non- Maxwellian equilibria in tokamak plasmas. Jungpyo (J.P.) Lee (Part 1) Michael Barnes (Part 2) Felix I.

DPG School The Physics of ITER Physikzentrum Bad Honnef, Energy Transport, Theory (and Experiment) Clemente Angioni

Towards Multiscale Gyrokinetic Simulations of ITER-like Plasmas

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas

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

Observations of Rotation Reversal and Fluctuation Hysteresis in Alcator C-Mod Plasmas

On tokamak plasma rotation without the neutral beam torque

Development and Validation of a Predictive Model for the Pedestal Height (EPED1)

Coupled radius-energy turbulent transport of alpha particles

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

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

1 THC/P4-01. Shear flow suppression of turbulent transport and self-consistent profile evolution within a multi-scale gyrokinetic framework

Gyrokinetic Theory and Dynamics of the Tokamak Edge

Theory Work in Support of C-Mod

Spontaneous tokamak rotation: observations turbulent momentum transport has to explain

Light Impurity Transport Studies in Alcator C-Mod*

Triggering Mechanisms for Transport Barriers

Global particle-in-cell simulations of Alfvénic modes

Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport

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

Gyrokinetic Simulations of Tokamak Microturbulence

Experimental Evidence of Inward Momentum Pinch on JET and Comparison with Theory

Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling

Particle-in-cell simulations of electron transport from plasma turbulence: recent progress in gyrokinetic particle simulations of turbulent plasmas

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

Poloidal Variation of High-Z Impurity Density in ICRF- Heated Alcator C-Mod Plasmas

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

Density Peaking At Low Collisionality on Alcator C-Mod

Inter-linkage of transports and its bridging mechanism

Gyrokinetic Transport Driven by Energetic Particle Modes

Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas

Progress and Plans on Physics and Validation

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

in tokamak plasmas Istvan Pusztai 1 Jeff Candy 2 Punit Gohil 2

Microtearing Simulations in the Madison Symmetric Torus

Global Nonlinear Simulations of Ion and Electron Turbulence Usintg a Particle-In-Cell Approach

Rotation and Neoclassical Ripple Transport in ITER

BO Non-Local Heat Transport, Rotation Reversals and Up/Down Impurity Density Asymmetries in Alcator C-Mod Ohmic L-mode Plasmas. J.E.

UCIrvine. Gyrokinetic Studies of Turbulence Spreading IAEA-CN-116/TH1-4

Critical gradient formula for toroidal electron temperature gradient modes

NumKin, Strasbourg, October 17 th, 2016

Modeling of ELM Dynamics for ITER

Understanding and Predicting Profile Structure and Parametric Scaling of Intrinsic Rotation. Abstract

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

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

EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY*

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

The gyrokinetic turbulence code GENE - Numerics and applications

Theory for Neoclassical Toroidal Plasma Viscosity in a Toroidally Symmetric Torus. K. C. Shaing

Electron Transport and Improved Confinement on Tore Supra

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model

Edge Momentum Transport by Neutrals

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

Bursty Transport in Tokamaks with Internal Transport Barriers

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

Gyrokinetic Turbulence in Tokamaks and Stellarators

Multiscale, multiphysics modeling of turbulent transport and heating in collisionless, magnetized plasmas

DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING

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

Turbulence in Tokamak Plasmas

Modification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas

Gyrokine.c Analysis of the Linear Ohmic Confinement Regime in Alcator C- Mod *

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

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

Mechanisms for ITB Formation and Control in Alcator C-Mod Identified through Gyrokinetic Simulations of TEM Turbulence

Coarse-graining the electron distribution in turbulence simulations of tokamak plasmas

W.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA

Non-diffusive Momentum Transport in JET H-mode Regimes: Modeling and Experiment

Validation studies on local gyrokinetic simulations of tokamak ITG-TEM driven turbulent transport

Observation of Co- and Counter Rotation Produced by Lower Hybrid Waves in Alcator C-Mod*

Electromagnetic Turbulence Simulations with Kinetic Electrons from the the Summit Framework

Intrinsic rotation reversal, non-local transport, and turbulence transition in KSTAR L-mode plasmas

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

Ohmic and RF Heated ITBs in Alcator C-Mod

Predicting the Rotation Profile in ITER

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

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

Experimental test of the neoclassical theory of poloidal rotation

International Workshop on the Frontiers of Modern Plasma Physics July On the Nature of Plasma Core Turbulence.

Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

Fine-Scale Zonal Flow Suppression of Electron Temperature Gradient Turbulence

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is

GA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY

Comparison of Deuterium Toroidal and Poloidal Rotation to Neoclassical Theory in the DIII-D Tokamak

On the Physics of the L/H Transition

2017 US/EU Transport Task Force Workshop April 26 th 2017 Williamsburg, VA

Formation and Back Transition of Internal Transport Barrier in Reversed Shear Plasmas

Characteristics of the H-mode H and Extrapolation to ITER

Non-perturbative statistical theory of intermittency in ITG drift wave turbulence with zonal flows

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

Dependences of Critical Rotational Shear in DIII-D QH-mode Discharges

Plasma Science and Fusion Center

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

Shear Flow Generation in Stellarators - Configurational Variations

Transcription:

Mechanisms of intrinsic toroidal rotation tested against ASDEX Upgrade observations William A. Hornsby C. Angioni, E. Fable, P. Manas, R. McDermott, Z.X. Lu, S. Grosshauser 2, A. G. Peeters 2 and the ASDEX Upgrade Team Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstrasse 2, 85748 Garching, Germany 2 University of Bayreuth, Bayreuth, Germany

Introduction Flows and flow shear regulate turbulence and can stabilise large scale MHD modes. Intrinsic rotation - No external torque, profiles determined purely by transport processes -> Still many open questions. Flow reversals - as seen on TCV, C-Mod, ASDEX Upgrade, MAST and KSTAR Can observed flow gradients be achieved? Which mechanisms are dominant? Database of ~9 ASDEX Upgrade profiles provides a testbed for the generation mechanisms of intrinsic flow McDermott et al, Nucl. Fusion (24), Hornsby et al, Nucl Fusion (27). Gyro-kinetic study using GKW (gkw.bitbucket.com). Many profiles encourages a quasi-linear approach, supported by nonlinear turbulence simulations. 2

Momentum transport Total toroidal momentum flux: R v th n i = u + RV u + neo + res Neoclassical background flow - Barnes, PRL 3, J Lee NF 4 Parallel velocity shear Peeters PoP 5 Coriolis pinch Peeters PRL 7 Hahm PoP 7 ExB shearing Dominguez, PFB 93 Garbet PoP 2 Gurcan PoP 7 Casson PoP 9 Waltz PoP 9 Up-down equilibrium asymmetry - Camenen PRL 9 Higher order parallel derivatives - Sung PoP 3, Stoltzfus-Dueck PoP 7 Profile shearing - Camenen, NF, Buchholz PoP 4, Waltz PoP Intensity profile effects Gurcan et al, PoP 2 Magnetic shear profile effects ZX Lu NF 5 3

Local 4

Introduction Intrinsic Momentum linked to breaking of symmetry along the field line in a Tokamak. Systematically investigate symmetry breaking mechanisms: Local Neoclassical background flows - Gyro kinetic code GKW interfaced with neoclassical code, NEO (Belli et al, PPCF 28, Belli et al, PPCF 22) Up-down equilibrium asymmetry Coriolis pinch Higher order parallel derivatives Perpendicular ExB flow shear Radially Global Profile shearing - Radial variations of Temperature, density and their gradients. Intensity profile effects - Radial variation of turbulence. Magnetic shear profile effects - Radial variation of the q-profile 5

GKW-NEO - Predicted u and experimental profiles R Total momentum flux: v th n i = u + RV u + neo + res = This term Balances with these terms Heat flux: Q i = it Prandtl number: Can maintain a predicted rotation gradient: u = i Q i Pr R L Ti Pr = / i Prandtl number varies weakly with plasma parameters:.5-.5 6

AUG Ohmic L-mode database and modes V [km/s T n [ 9 m 3 φ e & T i [kev e u at =.35 5 4 3 2 3 2 2 2..5.5. T =.35 Peaked (u >) Co-current (u>) Hollow (u < ) Counter-current (u < ).2.4.6.8 ν i* Wide range of plasma parameters - densities, temperatures, collisionality Flux-tube simulations with: Kinetic electrons Boron impurity species Realistic geometry Collisions 5 simulations per database point for two radial positions. Calc. Prandtl number Calc. Coriolis pinch Calc. up-down asymmetry Calc. Neoclassical effects Calc. Sung residual: @ @ Frequency, ω [v th i /R.5.5.5 =.35 =.5 ITG TEM.5.2.4.6.8.2.4 ν * [ν ii q/ε 3/2 φ 2 k i =.42 2 Pred. ITG Pred. TEM 3 k ρ 7

Toroidal flows» Radial force balance - n i Z i e( ~ E + ~ V i ~ B)=rP i =r n i Z i e( E ~ + V ~ B) ~ rp» with some manipulation, the toroidal flow is: t = ~ V r = @ @ p + n i q i dp i d p q ~ V r ExB flow Diamagnetic flow Poloidal flow Determined by neoclassical physics Collisions + Geometry 8

Toroidal flows» Radial force balance - n i Z i e( ~ E + ~ V i ~ B)=rP i =r n i Z i e( E ~ + V ~ B) ~ rp» with some manipulation, the toroidal flow is: t = ~ V r = @ + dp Usually neglected i q V ~ because: r @ p n i q i d = p i /R << ExB flow Diamagnetic flow Poloidal flow Determined by neoclassical physics Collisions + Geometry 9

Momentum transport - with background flows - symmetry breaking In very simple form, the total momentum flux can be written like: s = E,s u s + V E,s u d,s @! neo @r + V d,s! neo + res,s ExB terms have equivalent terms with respect to the neoclassical flows u = R v thi E ExB flow u neo = R v thi! neo u = R2 @ E v thi @r Parallel velocity gradient u neo = @! neo @r = R2 @! neo v thi @r Since equilibrium (time static) quantities, they are grouped with residual stress.

Flux-Tube - Predicted and experimental u.2 v =,u = t = ~ V r = @ @ p + n i q i dp i d p q V ~ r.2 GKW QL turbulent flux used to calculate the ExB flow gradient. u [R 2 /v th i.4.6.8.2.4.6 T =.35 ν * [ν ii q/ε 3/2 T =.35 GKW NEO, u ExB EXP, u tot Can maintain a R predicted rotation gradient: Total momentum flux: = u Residual from updown + RV u + neo + res v th n i asymmetry u = i Q i Pr s = E,s u s + V E,s u d,s R L Ti Heat flux: @! neo @r Prandtl number: + V d,s! neo + res,s Q i = it Pr = / i

Flux-Tube - Predicted and experimental u.2 v =,u = u ExB +u dia t = ~ V r = @ @ p + n i q i dp i d p q V ~ r u tot.2 u Exper data22 GKW QL turbulent flux used to calculate the ExB flow gradient. u [R 2 /v thi.4.6.8 Corrected by Boron diamagnetic flow gradient We also have to add this (as calculated by NEO).2 T =.35 Total momentum flux: s = E,s u s + V E,s u d,s @! neo @r + V d,s! neo + res,s.4 ν * [ν ii q/ε 3/2 Can maintain a R predicted rotation gradient: = u Residual from updown + RV u + neo + res v th n i asymmetry u = i Q i Pr R L Ti Heat flux: Prandtl number: Q i = it Pr = / i 2

Flux-Tube - Predicted and experimental u - Coriolis, finite R s v th n i = E,s u s + RV E,s u + neo + res,s... res and from up-down asymmetry r parallel derivatives..3 = i /R.8.5 T =.35 Predicted flow gradient, u [R 2 /v th i.2...2.3 Neoclassical Coriolis Up down equil Neoclassical (total flow) Finite rho parallel ν = ν q/ε 3/2 * ii Coriolis pinch rhostar corrections Terms usually ignored in fluxtube geometry for ordering reasons e.g @ @ Up-down EQ asymmetry z [m.4.3.2...2.3.5.6.7.8.9 r [m 3

Flux-Tube - Predicted and experimental u - Coriolis, finite R s v th n i = E,s u s + RV E,s u + neo + res,s... res and from up-down asymmetry r parallel derivatives. = i /R.8.5.3 T =.35.2 Predicted flow gradient, u [R 2 /v th i.2...2.3 Neoclassical Coriolis Up down equil Neoclassical (total flow) Finite rho parallel ν * = ν ii q/ε 3/2 u [R 2 /v th i.2.4.6.8.2.4.6 T =.35 ν * [ν ii q/ε 3/2 GKW NEO, u ExB EXP, u tot GKW NEO, u tot Combined total flow gradient, u under-predicted by.5-. depending on collisionality. Terms are all same magnitude. Hornsby et al, NF 27 =.35 4

Flux-Tube - Density profile variations Neoclassical flow gradient is the dominant parameter: @! neo @r @2 T i @r 2.5. ρ t =.35 ρ t =.5 Using a fit over the database - Predict the 2nd der. required = 2P rr/l ne AR/L Ti u E B u ExB [v th /R 2.5.5..5 Where = R2 @ 2 n e n e @r 2.2.25 Fit gradient, A.5.5 ω d,ζ / r [v th i /R 2 5

Flux-Tube - Density profile variations n e [ 9 5 4 3 2 Neoclassical flow gradient is the dominant parameter: @! neo @r @2 T i @r 2 (R 2 /n e ) 2 n e / r 2 2 8 6 4 2 ρ =.5 2nd der. meas T =.5 need =.35 need ρ =.35 meas. T (R 2 /ne ) 2 n e / r 2.2.4.6.8.2 5 5.9 2.s 2. 2.3s 2.3 2.5s 2.5 2.7s 2.7 2.9s 2.9 3.s 3. 3.3s 3.3 3.5s ρ p High resolution reflectometry measurements ρ#3236 p Many thanks: A Medvedeva et al.2.4.6.8 6-x larger 2nd derivatives required from nominal params. Corrugations in ne exist in the region of interest. Need to 5- times larger. Amplitudes too small to generate flows large enough to explain observations. n e /n e ( =.35) 2 4 6.5.5.2.8.6.4.2 n e n e +err n e err 2nd der. =.35 =.35 needed 2nd der. =.5 =.5 needed u exp.2.4.6.8 6

Background ExB shearing u = i Q i Pr R L Ti u can also be increased by reduction on Pr For a selection of points, nonlinear flux tube simulations, with and without perpendicular ExB shearing. ExB shearing rate given by experimental u ; E =( /q)u ExB Effective Prandtl number reduction by perpendicular flow shear also small - Approx -2% from Nonlinear simulations. Momentum diffusion term can be written, i = m i n i u + M E Prandtl number, P eff,r = χ φ /χ i.85.8.75.7.65,eff = +( /q)m Pr eff =,eff / i Dashed lines are QL calc value used in database evaluation..2.4.6.8. γ E = (ε/q) u ExB 7

Radially Global 8

Introduction Intrinsic Momentum linked to breaking of symmetry along the field line in a Tokamak. Systematically investigate symmetry breaking mechanisms: Flux-tube Neoclassical background flows - Gyro kinetic code GKW interfaced with neoclassical code, NEO (Belli et al, PPCF 28, Belli et al, PPCF 22) Up-down equilibrium asymmetry Coriolis pinch Higher order parallel derivatives Perpendicular ExB flow shear Radially Global Profile shearing - Radial variations of Temperature, Density and their gradients. Intensity profile effects - Radial variation of turbulence. Magnetic shear profile effects - Radial variation of the q-profile 9

Global mechanisms - Setup and profiles Do global effects make up the difference seen? Concentrate on three profiles from Shot Number #27-27 Use profiles as input to Global nonlinear turbulence calculation - Significantly more expensive than flux-tube simulations. n e 6 x 9 Linearly (fluxtube) at rho=.5 - TEM -> ITG transition, at rho=.35 always ITG. T e /T i goes from 2.24 to.54, 5 4 3 2.2.4.6.8 Time Radial Domain Density ramp - Increasing collisionality. = ii q/ p 3 =.5.75 Flux-tube predictions for these points at T =.35 u = -.2 u = -.27 u = -. Missing ~.4-. Do global turbulence simulations replicate the gradients observed and the flat-hollow-flat transition? Toroidal flow, v ζ..5.5..2.4.6.8 u.5.5 Flow, u Flow gradient, u.5.2.4.6.8 2

Global mechanisms - Setup and profiles Simulation parameters: Nx = 28-52 depending on Nv = 64, Nmu = 8, Ns = 6 Maximum mode number: k i =.4 Toroidal mode number spacing, -5 depending on Boundaries have damping buffers, 5-2 grid points. Circular flux surfaces. R/LTe = 5 (approximate value at centre of domain) all other profiles are experimental. Flux-tube predictions for these points at T =.35 u = -.2 u = -.27 u = -. Missing ~.4-. Toroidal flow, v ζ..5.5..2.4.6.8 u.5.5 Flow, u Radial Domain Flow gradient, u Radial Domain.5.2.4.6.8 2

Global mechanisms - realistic normalised gyro-radius.9.8.7 Integrated from Π i /Q i Exp. flow profile Exp. error bars GKW, u final state left buffer right buffer Adiabatic electrons. One can, early in a nonlinear simulation calculate the residual stress and estimate flow gradient u = i Q i Pr R L Ti Flow, u [v th i.6.5.4 Prandtl number, Pr=.63 from quasi-linear simulation. Flow profile calculated from residual from this gives good experimental agreement.3 Agreement with flow profile in this case is good..2...2.3.4.5.6.7.8 r/a =.5 Adiabatic electrons (Dashed lines) give peaked profiles - Flow profiles reversed. However, reversed, or flat, experimental flow profiles are not reproduced. 22

Global mechanisms - Flow profiles Kinetic electron simulations (Solid lines) give hollow rotation profiles. Like the majority of the experimental profiles. Adiabatic electrons (Dashed lines) give peaked profiles - Flow profiles reversed. Linear residual stress has same sign. Why reversal? u [v thi.5..5.5 =.5 = i /R artificially large - allows a scan of parameters on expensive global simulations. With kinetic electron, scaling with is weak Weaker than adiabatic scaling with idealised profiles (Buchholz et al, POP 22)..5.2.5..5.2 u.6.4.2.2 u = -.6 to -.7 seen in the centre of the domain. Large enough to bridge the difference in observations and flux tube mechanisms..4 45.6 39 5.8.5..5.2 Radial coordinate, ψ [r/r 23

Global mechanisms - realistic normalised gyro-radius Flow, u [v th i.2..8.6 Exp. flow profile GKW, u final state Integrated from Π i /Q i left buffer right buffer One can, early in a nonlinear simulation calculate the residual stress and estimate flow gradient u = i Q i Pr Prandtl number, Pr=.7 R L Ti Flow profile calculated from residual from this gives no experimental agreement Agreement with flow profile in this case is bad.4.2..2.3.4.5.6.7.8 r/a =.5 However, reversed, or flat, experimental flow profiles are not reproduced. 24

Global mechanisms - Density profile variation With adiabatic electrons - No particle flux - No density profile variation. With kinetic electrons - Particle flux - Density profile time-evolves. - Increases the value of 2 R 2 @ 2 n e n e @r 2 - Changes the residual stress, i,res = i,res (n e,n e,n e,t i,ti,ti,...) - Intrinsic flow profile slowly evolves accordingly - u increases Slice the simulation: n e /n e..9.8.7.2.4.6.8. Heat flux, Q i [ρ * v th,i 8 6 4 2 2 4 6 8 Time, t [R/v th,i Into time slices t N 4R /v th,i And radial slices Calculate mean: u r.2a R 2 @ 2 n e n e @r 2 U [v th i.5.5..5.2.4.6.8 r/a 25

Global mechanisms - Density profile variation With adiabatic electrons - No particle flux - No density profile variation.. With kinetic electrons - Particle flux - Density profile time-evolves. - Increases the value of - Changes the residual stress, i,res = i,res (n e,n e,n e,t i,ti,ti,...) - Intrinsic flow profile slowly evolves accordingly - u increases Heat flux, Q i [ρ * v th,i 2 8 6 4 2 2 4 6 8 Time, t [R/v th,i R 2 @ 2 n e n e @r 2 Slice the simulation: Into time slices t N 4R /v th,i And radial slices r.2a Calculate mean: u R 2 @ 2 n e n e @r 2 n e (r)/n i,res [m i n i v thi R 2 * u [v thi.5.95.9.85.6.4.2 -.2 -.4 -.6.2. -. -.2.2.4.6.8.2.4.6.8.2.4.6.8 r/a 26

Global mechanisms - Density profile variation Residual stress is a function of many variables Here we vary only i,res = i,res (n e,n e,n e,t i,t i,t i,...) n e,n e,n e with time. (The Krook operator fixes the background temperature profile).4.2..9.8 Steepening of profile is seen periodically in measurements. Profile curvature notoriously difficult to measure..7.2 u.8 u [v th /R.2.4.6.8 u.8 R2 @ 2 n e n e @r 2.6.5.4.3.2. u.4.6.8.2 R 2 n e @ 2 n e @r 2 2 3 4 5 6 t [s 5 5 5 (R 2 /n)d 2 n/dr 2 T =.5 Time traces of u at from Shot number #27 27

Global mechanisms - Density profile variation Residual stress is a function of many variables Here we vary only background temperature profile).4.2 i,res = i,res (n e,n e,n e,t i,t i,t i,...) n e,n e,n e with time (The Krook operator fixes the..9 R 2 n e @ 2 n e @r 2 5 (R 2 /n e ) 2 n e / r 2 2 8 6 4 2 =.5 2nd der. meas =.5 need =.35 need =.35 meas..8 2 u [v th /R.2.4.7.6.5.4 Consistent with measurements, gives: u.2 4 6.2.5.5 u exp.6.8 u 5 5 5 (R 2 /n)d 2 n/dr 2.8 R2 @ 2 n e n e @r 2.3.2. Mechanism much stronger than neoclassical flow effects. u. n e /n e ( =.35).8.6.4.2 n e n e +err n e err 2nd der. =.35 =.35 needed 2nd der. =.5 =.5 needed.2.4.6.8 28

In conclusion A systematic study of intrinsic momentum generation mechanisms was performed on a large database of AUG Ohmic L-mode shots Linear and nonlinear gyro kinetic simulations in both flux-tube and global geometry were compared with experimental observations. Combined mechanisms described by flux tube simulations falls short of experimental u by a factor 3-5. Global simulations with kinetic electrons to quantify profile shearing effects show significant flow gradients - u =.6-.2 Density profile curvature is seen in the global and flux-tube cases, to be the significant parameter. However, profile shearing is seen to be much more sensitive to curvature. Parameterisation gives good qualitative agreement with experiment. Going forward - Global-local analysis (c.f Zhixin Lu tomorrow morning) -> Towards a quasi-linear model. Many thanks 29

GKW-NEO - Implementation Implementation of Barnes-Parra model M. Barnes, F. I. Parra, et. al, Phys. Rev. Lett.,555 Interface of Neoclassical transport code NEO with GKW Neoclassical distribution function is a correction to the equilibrium Maxwellian f = F + f.35.3 GKW NEO GS2 NEO a( k a ) GKW NL Region of database interest F = F M + f NEO = NEO + f NEO Neoclassical part calculated by Eulerian code, NEO Turbulent part solved for by non-linear Gyro-kinetic code, GKW 2 with corrections due to the perturbed background distribution function. f Flux ratio, Π i /Q i.25.2.5..5 Symmetry breaking mechanism that produces momentum transport. E A Belli and J Candy 22 Plasma Phys. Control. Fusion 54 55 2. A.G Peeters et al. Computer Physics Communications, 8, 265 (29) 2 Normalised collision frequency, ν = ν q/ε 3/2 * ii 3

Global mechanisms - Flow profiles and exp. comparison k measures the level of mode asymmetry along the field line n Momentum flux here is given by: Residual stress can be calculated by damping the nonlinearly generated n= flow or early in the nonlinear phase. u / <k >.8.6.4.2.2 <k R >= s = u (Nonlinear global) 5x<k > linear flux tube, k θ ρ i =.42 <k > (nonlinear global) R/L n <k > (nonlinear global) Z X @ @s ds E,s u s + res,s u [v th i..8.6.4.2.4 u gkw = -.6 u gkw = -.6 u gkw = -.4.2 u exp = -.4 u exp = -.2 u exp = -.35.2.4.6.8..2.5..5.2.25 ψ = r/r.4.2.5..5 ψ = r/r.2.2.25.5..5 ψ = r/r.2.25 Boundary conditions (no slip u = at edges) restrict shape of flow. Restrict comparison to middle of the domain. u large enough to reproduce experiment in some cases...8.6.4.6.8 u (r) <k > R L n.5..5.2.25 ψ [r/r k profile well reproduced by series of radial flux tube simulations input tilt angle and nonlinear u Profile shearing important component Density gradient variation -> Large change in i /Q i 3

Backup 2 - Integrated profiles from u u = i Q i Pr R L Ti.2 u II GKW u exp u from Π/Q.4.2 u from Π/Q u from GKW Where we assume Pr=.7.2 u is well reproduced u [v th i.4.6 u.2.8.4.8.7 U GKW U exp U integrated from Π/Q.6.4 u from Π/Q u from GKW..5..5.2.25 ψ = r/r.6..2 ψ = r/r.9.8 u integrated from Π/Q u GKW final u exp.5 u from Π/Q u GKW final.6.2.7 U.5.4 u.2 u [v thi.6.5.4 u.5.3.2.5..5.2 ψ = r/r.4.6.8.5..5.2 ψ = r/r.3.2..5..5.2 ψ = r/r.5.5..5.2 ψ = r/r APS DPP 26 San Jose, California 32