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

Similar documents
Density Peaking At Low Collisionality on Alcator C-Mod

C-Mod Transport Program

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

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

Characteristics of the H-mode H and Extrapolation to ITER

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

Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod

Light Impurity Transport Studies in Alcator C-Mod*

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

TURBULENT TRANSPORT THEORY

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

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

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

Mechanisms of intrinsic toroidal rotation tested against ASDEX Upgrade observations

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

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

Multispecies density peaking in gyrokinetic turbulence simulations of low collisionality Alcator C-Mod plasmas

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

Theory Work in Support of C-Mod

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

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

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

Understanding physics issues of relevance to ITER

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

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

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

Predicting the Rotation Profile in ITER

Gyrokinetic Transport Driven by Energetic Particle Modes

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

DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING

Coupled radius-energy turbulent transport of alpha particles

Correlation Between Core and Pedestal Temperatures in JT-60U: Experiment and Modeling

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

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

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

JP Sta,onary Density Profiles in Alcator C Mod

Plasma instability during ITBs formation with pellet injection in tokamak

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

Self-consistent modeling of ITER with BALDUR integrated predictive modeling code

Electron Transport and Improved Confinement on Tore Supra

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

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

Ohmic and RF Heated ITBs in Alcator C-Mod

Inter-linkage of transports and its bridging mechanism

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

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

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

Impact of Toroidal Flow on ITB H-Mode Plasma Performance in Fusion Tokamak

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

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

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

Helium ELMy H-modes in Alcator C-Mod in Support of ITER Helium Operating Phases

On tokamak plasma rotation without the neutral beam torque

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

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

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

PSFC/JA D.R. Ernst, N. Basse, W. Dorland 1, C.L. Fiore, L. Lin, A. Long 2, M. Porkolab, K. Zeller, K. Zhurovich. June 2006

Non-local Heat Transport in Alcator C-Mod Ohmic L-mode Plasmas

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER

GA A26874 ITER PREDICTIONS USING THE GYRO VERIFIED AND EXPERIMENTALLY VALIDATED TGLF TRANSPORT MODEL

MHD Pedestal Paradigm (Conventional Wisdom)

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

Microtearing Simulations in the Madison Symmetric Torus

Gyrokinetic Simulations of Tokamak Microturbulence

Progress and Plans on Physics and Validation

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

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

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

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

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

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

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

Modeling of ELM Dynamics for ITER

Overview of Alcator C-Mod Research

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

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

On the ρ Scaling of Intrinsic Rotation in C-Mod Plasmas with Edge Transport Barriers

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

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

Non-ohmic ignition scenarios in Ignitor

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Core Transport Properties in JT-60U and JET Identity Plasmas

Summary of CDBM Joint Experiments

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

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team*

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

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

Tuomas Tala. Core Density Peaking Experiments in JET, DIII-D and C-Mod in Various Operational Scenarios Driven by Fueling or Transport?

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

Shear Flow Generation in Stellarators - Configurational Variations

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

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

On the Physics of Intrinsic Flow in Plasmas Without Magnetic Shear

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

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

Turbulent Transport Analysis of JET H-mode and Hybrid Plasmas using QuaLiKiz, TGLF and GLF23

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

Transcription:

Low-collisionality density-peaking in GYRO simulations of C-Mod plasmas D. R. Mikkelsen, M. Bitter, K. Hill, PPPL M. Greenwald, J.W. Hughes, J. Rice, MIT J. Candy, R. Waltz, General Atomics APS Division of Plasma Physics Annual Meeting Atlanta, 2-6 November 29

Overview of density peaking simulations Angioni, et al., Phys. Plasmas 1 (23) 3225. GLF23 simulations apparently explain observations. Higher collisionality reduces the anomalous pinch due to trapped electrons. Angioni, et al., Phys. Plasmas 12 (25) 11231. GS2 quasilinear gyrokinetic estimates of particle flux. raising collisionality turns off the pinch, but the transition is much too early. poor mode choice: low k θ ρ i ~.2 (motivated by TEM heat transport study) Mikkelsen, et al., APS-DPP 27; nonlinear GYRO, C-Mod H-mode pinch is driven by modes with k θ ρ i >.5 - missing from quasilinear work! Maslov, et al., Nucl. Fusion 49 (29) 7537, QL peaking in JET H-modes. different mode choice: modes at max. growth rate do generate a pinch. raising T e /T i increases the pinch (if ITG is still the dominant instability). Angioni, et al., Phys. Plasmas 16 (29) 672. nonlinear GYRO for AUG: k-spectrum of particle flux similar to C-Mod. collisionality and energy dependence in analytic quasilinear expression.

Is Peaking Factor the Same for D & H? Different peaking factors for D & T in ITER could be important: stronger tritium peaking would make tritium fueling easier (and vice versa). Phase-contrast-imaging system on C-Mod enables core n H /n e measurement. Data indicates that core n H /n e is lower than edge n H /(n D +n H ) (from D α light); and plausible Z eff can't explain the diffference. A dedicated experiment with controlled H puffing is planned with n H ~n D. GYRO simulations can be used to derive the density profile shape that is 'predicted' to produce null particle flux, when the pinch balances diffusion; this applies to steady-state C-Mod plasmas with no core fuelling. Quasilinear estimates of particle flux are unreliable, so nonlinear 'global' simulations are used here.

C-Mod peaked-density regime Discovered with JFT-2M shape: produced low-density H-mode plasmas. low κ, high δ lower >.75, lower target density. Pedestal density is especially low, and T ped is high,.8-.9 kev Pedestal is wider, infer larger D causes lower n e, higher T e ELMs. Higher density ohmic EDA H-modes with same profile shape are not unusual. Density peaking also seen in standard shape, with lower I p. Surprise result: Density profile is peaked; in RF-heated H-mode plasmas peaking is never seen at higher densities. ITBs have central density peaking, but flat periphery; this regime has flat central region and a density gradient for >.5

Lower Density H-Modes Have Peaked Profiles Greenwald, et al., Nuclear Fusion 47 (27) L26 Lower L-H threshold density ELMs seem to reduce rate of density rise in H-mode Whatever the cause: Standard H-mode n e /<n e > = 1.1-1.2 L n >> a, R/L n ~, R/L Te ~ 6-7 Low-Density H-mode n e /<n e > = 1.5 R/L n ~ 3-4, R/L Te ~ 6-7

Difference In Profile Shape Is Notable Peaking is seen over outer 6% of plasma radius H-mode profiles evolve quickly; τ << a/v WARE Transport in center of plasma may be affected by sawteeth These are of large amplitude; δt e /T e ~ 25% Radii chosen to characterize peaking in ASDEX-U are =.4 Sawtooth Inversion Radius =.8 appropriate for C-Mod profiles

Increased Density Peaking At Low Collisionality Observed For ICRF Heated H-Modes In C-Mod New Shape Standard Shape

C-Mod Data Helps Break Covariance Between ν eff and n/n G ITER ITER ICRF Only ICRF Only ν EFF = ν ei /ω D.1RZ EFF <n e >/<T e > 2

T i Differs from T e at Low Density Low collisionality is linked to other important changes in C-Mod plasmas. T i profile is less peaked than T e in low-density H-mode plasmas. T e -T i can be large, but Q ie is < 1 MW. central T i is apparently not consistent with the neutron rate, but is the deuterium distribution Maxwellian at 2 nd harmonic of ICRH? Measured L Ti is longer than L Te for ~.6 relaxed T i profile at low density reduces the ITG drive, but Higher T e /T i increases ITG drive. Kinetic electron drive depends strongly on collisionality at these densities. The relative importance of different microinstability drives changes as collisionality is reduced, so the details may differ from JET and AUG.

Standard H-mode Flat density profile n e ()~3.3x1 2 m -3

n e ()~2.1x1 2 m -3 Peaked density H-mode

n e (1 2 /m 3 ) 3 2 1 T i profile relaxes as density drops 1821327 1821331 176149 17831 1761417 1812521.2.4.6.8 1 As density is lowered the density peakedness rises, and T i () drops (T i is less tightly coupled to T e at all radii). Consequently, the L Ti is longer than L Te for ~.6 The relaxed T i profile at low density reduces the ITG drive, very close to the ITG threshold for the lowest density cases. 3 2 T i (kev) 1 1821327 1821331 176149 17831 1761417 1812521.2.4.6.8 1

Simulation Procedure Electrostatic turbulence, with kinetic ions and electrons. Measured T e (r) and n e (r) are used in GYRO simulations presented here. The measured T i (r) has been used but these have stable regions, so oscillations in R/L Ti are removed to smooth the profiles. Simulations have only deuterium and electrons, but the 'resistive' Z eff value is used in the collisionality. Shaped geometry is used. ExB shear is ignored (but expected to have a small effect). As the density gradient is varied, the particle flux changes; this is used to estimate the R/Ln that would produce null particle flux at each radius. The extrapolated R/Ln is integrated to find the 'predicted' density profile.

3 2 T i (kev) 1 T i modifications are small 1821327 1821331 176149 17831 1761417 1812521 3 2 T i (kev) 1 1821327 1821331 176149 17831 1761417 1812521 flattened R/L Ti profles.2.4.6.8 1.2.4.6.8 1 Measured T i (r) is matched near center and edge, R/L Ti is smoother in between. 1 R/L Ti 1821327 1821331 176149 17831 1761417 1812521 1 R/L Ti 1821327 1821331 176149 17831 1761417 1812521 5 5.2.4.6.8 1.2.4.6.8 1

Stronger density peaking at low e.15.1.5! e -.5 1821327 @1.28 sec flat R/L Ti -.1 Exptl. ne R/Ln raised 3% -.15.3.4.5.6.7.8 1.2.4.6.8 1 Inward pinch is much stronger with lower collisionality below..2.1 1821327 @1.28 sec flat R/L Ti (exptl. " e )/3 n e (1 2 /m 3 ) 3 2 3 1821327 @1.28 sec flat R/L Ti Exptl. ne Extrapolated! e = 1821327 @1.28 sec flat R/L Ti! e -.1 -.2 Exptl. ne R/Ln raised 1% -.3.3.4.5.6.7.8 n e (1 2 /m 3 ) 2 Exptl. ne Extrap. exptl.! e Extrap. (exptl.! e )/3 1.2.4.6.8 1

D e (k! " s ) (arb. units) -.5 -.15 Higher k modes are responsible for the pinch.1.5 -.1 exp. # e # e /3 -.2.2.4.6.8 k! " s More modes contribute to the pinch at lower collisionality. Raising the density gradient reduces the pinch at all k θ ρ s. D e (k! " s ) (arb. units).15.5 -.5 -.15 Need to do some simulations with higher maximum k θ ρ s. -.2.2.4.6.8 k! " s Missing inward flux at low collisionality is probably larger than missing outward flux at high collisionality, so the present simulations probably underestimate the density peaking at the null flux condition..1 -.1 exp. R/L n R/L n *2.4 R/L n *2

a/l n, a/l Ti and Mix of Ions is Varied Results from six pairs of simulations are shown next. Use particle fluxes, Γ x, for the standard a/l n & lower a/l n of each pair to estimate the a/l n that would give Γ x =. Two sets of a/l Ti are used for each combination of ions. Need assessment of power dependence of peaking factor, simulations with more ITG drive may show less peaking. Only D, with standard a/l Ti and 1% boost. 5:5 D:H at all radii, with standard a/l Ti and 1% boost. 42:42:3 D:H:B at all radii, with 2% & 3% boost of a/l Ti. (dilution of hydrogenic isotopes reduces turbulence)

Extrapolation Exhibits Density Peaking! e.2.1 (a.u.) -.1 1.5 a/l ne 1.5 Std a/l n low a/l n DH_gT1.4.5.6.7 Std. al n low a/l n! e = root polynomial fit DH_gT1.4.5.6.7 a/l ne for Γ e = diverges where simulated fluxes cross: ~.41, but the extrapolation integrates to make only a small n e (r) jump. The smoother polynomial fit to the Γ e = root is not needed here. n e (r) (1 2 /m 3 ) 2.4 2.2 2 Std. a/l n low a/l n!= root polynomial fit DH_gT1.4.5.6.7

Electron Density Peaking is Robust 2.4 Electron density peaking is insensitive to variations in the ion species mix and to a wide range of transport powers. n e (r) (1 2 /m 3 ) 2.2 2 6 GYRO Q tot (MW) 3 D_gT1 DH_gT1 DHB_gT2 DHB_gT3.4.5.6.7.4.5.6.7

! D.2.1 (a.u.) -.1 1.5 1 a/l nd.5 Ion Fluxes Require Smoothing Std. a/l n low a/l n Std. smoothed low smoothed.4.5.6.7 Std. a/l n low a/l n! D = root polynomial fit D_gT1 D_gT1.4.5.6.7 Low-order (n=2,3) polynomial smooths the ion fluxes. Extrapolated root and n D (r) are similar to companion run's n e (r). Expect this for ambipolar ExB transport with one ion species. n D (r) (1 2 /m 3 ) 2.4 2.2 2 Std. a/l n low a/l n! D = polynomial fit D_gT1.4.5.6.7

! H.2.1 (a.u.) -.1 1.5 1 a/l nh.5 Hydrogen Density is Less Peaked Std. a/l n low a/l n Std. smoothed low smoothed DH_gT1.4.5.6.7 Std. a/l n low a/l n! H = root polynomial fit DH_gT1.4.5.6.7 Extrapolated Γ H = root has much lower values of a/l nh, so n H (r) peaking is lower than for the electron density, and n D (r) peaking is higher n H (r) (1 2 /m 3 ) 1.2 1 Std. a/l n low a/l n! H = polynomial fit DH_gT1.4.5.6.7

Deuterium is More Peaked than Hydrogen D & H density peaking is insensitive to the variation in the transport power. 1.2 n(r) (1 2 /m 3 ) 1 D DH_gT1 D DH H DH H DH_gT1.4.5.6.7

Improved Simulation Methodology A significant separation of a/l nx at all is needed. varying the overall a/l ne is undesirable, that changes Q tot. GYRO can handle multiple ions, so use 2-3 ion species with identical A,Z for each isotope. Make offsetting changes to a/l n so total density is unaffected. Same turbulent eddies affect both high- and low-a/l n 'species', so the dependence on a/l n is accurately captured in one run. Two 'species' define D and V pinch, three confirm linearity. This method works very well for trace impurities (see N.Howard poster) New run with extrapolated density profiles needed to confirm the prediction: the turbulent drive is affected by the new a/l n.

Summary of Isotope Peaking GYRO simulations exhibit collisionality-dependent peaking. Nonlinear work supports analytic quasi-linear estimates that may provide a detailed framework for understanding. See E. Fable, et al., PPCF 5 (28) 1155, and C. Angioni, et al., Phys. Plasmas 16 (29) 672 and PPCF 51 (29) 12417. D & H have different peaking factors in GYRO simulations. A C-Mod experiment to measure D&H peaking is planned. ITER simulations are needed to study D&T peaking. A more robust simulation methodology will be used in future.

'Predicting' Intrinsic Rotation C-Mod has long exhibited 'intrinsic' rotation with no (intended) momentum source (RF deposition may be preferential?). GYRO can calculate radial transport of toroidal momentum. [Waltz, et al., Phys. Plasmas 14 (27) 12257] Use it to assess the rotation generated by turbulence. Assume there is no external torque in the simulation domain. Look for the rotation profile that is consistent with null radial flux of toroidal momentum - i.e., consistent with steady rotation. The controlling GYRO input variable is actually E r ; NEO will be used to 'back out' the implied rotation speeds. The E r profile is modified iteratively to achieve null flux; for this problem, the radial gradient of E r is varied to find the root.

Null-flux Root has Smaller E r Gradient.4! mom (a.u.) a*(de r /dr) (kv/m) -.4 5-5 -1 Std. E r E4.3*grad-E r.4.5.6.7 Std. E r.3*grad-e r! mom = root E4-15 polynomial fit.3.4.5.6.7 de r /dr for Γ mom = diverges where simulated fluxes cross: ~.7, so smooth out the ragged root with a polynomial fit. Integrate the polynomial fit to find the profile of E r : E r (kv/m) 4 2-2 Std. E r.3*grad-e r fit to root E4.4.5.6.7

4 Qualitative 'Agreement' with Expt. 4 E4 E29 E r (kv/m) 2 E r (kv/m) 2 E r (kv/m) -2 4 2-2 Std. E r.3*grad-e r fit to root.4.5.6.7 Std. E r grad-e r =-2 fit to root E12.4.5.6.7-2 Std. E r.3*grad-e r fit to root.4.5.6.7 Higher rotation cases, '4 & '29 are 'predicted' to have higher rotation (implicit in E r profiles). The implied rotation profiles are expected to lie well outside the uncertainties of the v φ data. The prediction uncertainties are not yet estimated.

Improved Simulation Methodology-2 A significant separation of de r /dr at all is needed. integrate (Std. de r /dr - Constant) to create the secondary E r. This will change the ExB shear, so move de r /dr toward zero to avoid strengthening the ExB-shear turbulence quenching. New runs are in progress, but no results are available yet. At this point the turbulently generated intrinsic rotation is not sufficient to explain the observed rotation speeds - but there are other proposed mechanisms that may shoulder the burden. On the other hand, it appears that turbulently driven rotation is not small enough to ignore when building a complete picture.