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

Similar documents
GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D

UNDERSTANDING TRANSPORT THROUGH DIMENSIONLESS PARAMETER SCALING EXPERIMENTS

IMPACT OF EDGE CURRENT DENSITY AND PRESSURE GRADIENT ON THE STABILITY OF DIII-D HIGH PERFORMANCE DISCHARGES

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D

GA A27806 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D

GA A26474 SYNERGY IN TWO-FREQUENCY FAST WAVE CYCLOTRON HARMONIC ABSORPTION IN DIII-D

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

GA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J.

GA A23977 DETAILED MEASUREMENTS OF ECCD EFFICIENCY ON DIII D FOR COMPARISON WITH THEORY

GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE

GA A23428 IMPROVEMENT OF CORE BARRIERS WITH ECH AND COUNTER-NBI IN DIII D

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

GA A24016 PHYSICS OF OFF-AXIS ELECTRON CYCLOTRON CURRENT DRIVE

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS

CORE TURBULENCE AND TRANSPORT REDUCTION IN DIII-D DISCHARGES WITH WEAK OR NEGATIVE MAGNETIC SHEAR

Scaling of divertor heat flux profile widths in DIII-D

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

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D

GA A26785 GIANT SAWTEETH IN DIII-D AND THE QUASI-INTERCHANGE MODE

PROGRESS TOWARDS SUSTAINMENT OF INTERNAL TRANSPORT BARRIERS IN DIII-D

GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D

GA A27433 THE EPED PEDESTAL MODEL: EXTENSIONS, APPLICATION TO ELM-SUPPRESSED REGIMES, AND ITER PREDICTIONS

Role of Flow Shear in Enhanced Core Confinement

GA A26866 REDUCED ELECTRON THERMAL TRANSPORT IN LOW COLLISIONALITY H-MODE PLASMAS IN DIII-D AND THE IMPORTANCE OF SMALL-SCALE TURBULENCE

DIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by

proposed [6]. This scaling is found for single null divertor configurations with the VB

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas

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

GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

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

Simulation of Double-Null Divertor Plasmas with the UEDGE Code

Advances in the Physics Basis of the Hybrid Scenario on DIII-D

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE STABILITY IN DIII D

GA A22689 SLOW LINER FUSION

GA A23698 ELECTRON CYCLOTRON WAVE EXPERIMENTS ON DIII D

Transport Improvement Near Low Order Rational q Surfaces in DIII D

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

Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence

GA A23430 ADVANCED TOKAMAK PHYSICS IN DIII D

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

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL

GA A26686 FAST ION EFFECTS DURING TEST BLANKET MODULE SIMULATION EXPERIMENTS IN DIII-D

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT

PLASMA MASS DENSITY, SPECIES MIX AND FLUCTUATION DIAGNOSTICS USING FAST ALFVEN WAVE

GA A22636 RECENT H MODE DENSITY LIMIT EXPERIMENTS ON DIII D

GA A24166 SUPER-INTENSE QUASI-NEUTRAL PROTON BEAMS INTERACTING WITH PLASMA: A NUMERICAL INVESTIGATION

DEMONSTRATION IN THE DIII-D TOKAMAK OF AN ALTERNATE BASELINE SCENARIO FOR ITER AND OTHER BURNING PLASMA EXPERIMENTS

GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO

Predicting the Rotation Profile in ITER

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

DRIFTWAVE-BASED MODELING OF POLOIDAL SPIN-UP PRECURSOR AND STEP-WISE EXPANSION OF TRANSPORT BARRIERS

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

GA A24340 ELECTRON CYCLOTRON CURRENT DRIVE IN DIII D: EXPERIMENT AND THEORY

GA A27290 CALCULATION OF IMPURITY POLOIDAL ROTATION FROM MEASURED POLOIDAL ASYMMETRIES IN THE TOROIDAL ROTATION OF A TOKAMAK PLASMA

Generation of Plasma Rotation in a Tokamak by Ion-Cyclotron Absorption of Fast Alfven Waves

GA A26891 A FIRST PRINCIPLES PREDICTIVE MODEL OF THE PEDESTAL HEIGHT AND WIDTH: DEVELOPMENT, TESTING, AND ITER OPTIMIZATION WITH THE EPED MODEL

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

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

Scaling of divertor heat flux profile widths in DIII-D

Progress Toward High Performance Steady-State Operation in DIII D

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

Impurity Transport Studies of Intrinsic MO and Injected Ge in High Temperature ECRH Heated FTU Tokamak Plasmas

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas

GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS

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

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

DIII-D TOKAMAK MODELING OF THE RECYCLING PARTICLE FLUX AND ELECTRON PARTICLE TRANSPORT IN THE

INTERNAL TRANSPORT BARRIERS WITH

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

GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS

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

UPGRADED CALIBRATIONS OF THE THOMSON SYSTEM AT DIII D

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

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

Characteristics of the H-mode H and Extrapolation to ITER

GA A23797 UTILIZATION OF LIBEAM POLARIMETRY FOR EDGE CURRENT DETERMINATION ON DIII-D

GA A27418 THE ROLE OF ZONAL FLOWS AND PREDATOR- PREY OSCILLATIONS IN THE FORMATION OF CORE AND EDGE TRANSPORT BARRIERS

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI

GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK

GA A23116 PLASMA ROTATION INDUCED BY RF

Plasma Response Control Using Advanced Feedback Techniques

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

SciDAC CENTER FOR SIMULATION OF WAVE-PLASMA INTERACTIONS

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges

ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS

Fission-Fusion Neutron Source

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

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

Electron Transport Stiffness and Heat Pulse Propagation on DIII-D

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012

Transcription:

GA A311 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES by C.C. PETTY, M.R. WADE, J.E. KINSEY, R.J. GROEBNER, T.C. LUCE, and G.M. STAEBLER AUGUST 1999

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe upon privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

GA A311 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES by C.C. PETTY, M.R. WADE, 1 J.E. KINSEY, R.J. GROEBNER, T.C. LUCE, and G.M. STAEBLER This is a preprint of a paper submitted for publication in Physical Review Letters. Work supported by U.S. Department of Energy under Contracts DE-AC3-99ER563 and DE-AC5-96OR6 and Grant DE-FG3-9ER511 1Oak Ridge National Laboratory Lehigh University GENERAL ATOMICS PROJECT 333 AUGUST 1999

Petty et al. DEPENDENCE OF HEAT AND PARTICLE TRANSPORT Dependence of Heat and Particle Transport on the Ratio of the Ion and Electron Temperatures C.C. Petty, 1 M.R. Wade, J.E. Kinsey, 3 R.J. Groebner, 1 T.C. Luce, 1 and G.M. Staebler 1 1 General Atomics, San Diego, California 9186-568 Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-9 3 Lehigh University, Bethlehem, Pennsylvania 1815 Experiments in high confinement (H mode) plasmas on the DIII D tokamak show that the heat and particle transport are sensitive to the ratio of the ion and electron temperatures. Increasing the ion to electron temperature ratio decreases the electron and ion heat transport and the particle transport regardless of which temperature is being varied. A likely explanation of these results is the dependence of the ion temperature gradient instability on the ratio of the ion and electron temperatures. Plasmas of interest to magnetic confinement fusion can be thought of as comprising separate ion and electron fluids, each fluid with its own density and temperature. The ion and electron densities ( n i and n e ) are related by the overriding tendency of the plasma to remain electrically neutral, but the ion and electron temperatures ( T i and T e ) can be quite different since the thermal equilibration time between the two fluids may be longer than the energy confinement time of the plasma. A large body of previous work has shown that cross-magnetic-field diffusion of heat and particles (referred to as transport) is significantly reduced in plasmas with T i >> T e. Nearly all of the best confinement modes on tokamaks occur in plasmas with T i more than twice T e : the hot ion H mode (high confinement) [1] and VH mode (very high confinement) [], the supershot [3], and the negative magnetic shear regime [,5]. However, T i and T e are expected to be nearly equal in future ignition devices owing to the longer confinement times and strong electron heating from the fusion products. Therefore, if transport has a strong dependence on the ratio of the ion and electron temperatures, then projecting the favorable transport results from hot ion mode plasmas to future ignition devices may lead to too optimistic predictions for confinement. The experiments reported in this Letter are the first in which the ratio of the ion and electron temperatures is systematically varied to determine the effect on heat and particle transport. These experiments in ELMing (edge localized mode) H mode plasmas are in a regime relevant to future ignition devices, with nearly equal ion and electron temperatures and T i profiles close to marginal stability for the ion temperature gradient (ITG) mode. Three different T i / T e scans have been done, each of which addresses a specific question. First, a GENERAL ATOMICS REPORT GA A311 1

DEPENDENCE OF HEAT AND PARTICLE TRANSPORT Petty et al. T e scan at fixed T i is performed to examine whether the ion heat transport is influenced by the electrons. Second, the converse, a T i scan at fixed T e shows how the electron heat transport is affected by the ions. Third, the ratio of T i / T e is varied at fixed β (the ratio of the plasma and magnetic field pressures) to determine if heat transport is dependent upon how the plasma pressure is divided between the electron and ion fluids. The helium particle transport is also measured for several of the T i / T e scans. For all of these experiments, the plasma density, current, and magnetic field strength are held fixed. These experiments are done on the DIII D tokamak [6], parameters for which are major radius R = 1.68 m, minor radius a =.61 m, elongation κ = 1.8, plasma current I = 1.5 MA, and magnetic field strength B =.5 T. A single-null divertor plasma configuration is used, and the plasma is fueled by deuterium gas puffing and deuterium neutral beam injection (NBI). Three different forms of auxiliary heating are used to control T i and T e in these experiments. The ions are heated by up to.9 MW of NBI; a small portion of this NBI power is also absorbed by the electrons. The electron temperature is increased further using up to.5 MW of combined electron cyclotron heating (ECH) and fast wave direct electron heating [7]. For these experiments, the electron density and temperature profiles are measured by Thomson scattering, CO laser interferometers, and electron cyclotron emission. The ion temperature and effective ion charge ( Z eff ) profiles are determined from charge exchange recombination emission of carbon impurities. The radiated power ( P rad ) profile is measured using an array of foil bolometers. In the first experiment, the electron temperature is varied at fixed ion temperature, as seen in Fig. 1, and shows that confinement decreases with increasing T e. The electron temperature is scanned by 6% in this experiment using ECH and fast wave heating while the NBI power is also increased to keep T i fixed. The heating powers absorbed by the ions and electrons ( P i and P e ) are shown in column (a) of Table I along with the other global parameters. The data in Table I do not include fast particle contributions to the normalized beta [β N = β / (I / ab)] and the energy confinement time ( τ E ). Table I shows that the volume averaged n e and Z eff are held fixed to within 3% during the T e scan, with the thermal energy confinement time scaling like τ E th Te.±.. The thermal diffusivities ( χ ) for these discharges are determined from a radial power balance analysis, 1.5 (nt) / t + (q +.5ΓT) = Q, where q is the heat flux, Γ is the particle flux, and the heat sources and sinks are combined into Q. The transport calculations are carried out using the ONETWO code [8], which uses the measured n e, T e, T i, Z eff, and P rad profiles along with the magnetic geometry. The heat flux is assumed to be purely diffusive in this analysis, q = nχ T. The helium particle transport is determined by analyzing the evolution of the helium density profile shortly after a helium gas puff [9]. The transport analysis shows that the ion thermal diffusivity increases with increasing T e at fixed T i, demonstrating that the ion transport is not dependent solely upon the ion parameters but is also influenced by the electrons. Figure shows the change in the electron and ion thermal diffusivities as a function of normalized radius ( r / a) between the high T e GENERAL ATOMICS REPORT GA A311

Petty et al. DEPENDENCE OF HEAT AND PARTICLE TRANSPORT 6 (a) 6 (b) T e (kev)....6 T i (kev).8 1.....6.8 1. Fig. 1. Radial profiles of (a) electron temperature, and (b) ion temperature for the T e scan at fixed T i given in Column (a) of Table I. Table I: Global parameters for three temperature scans at fixed B and I : (a) T e scan at fixed T i, (b) T i scan at fixed T e, and (c) T i / T e scan at fixed β. Parameter (a) (b) (c) high T e low T e high T i low T i high T i / T e low T i / T e n e (1 19 m 3 ) 3.6 3.7. 3.9 3.6 3.7 Z eff..5..5.3. th β N [%/(MA/mT)] 1.11 1. 1.39 1.9 1.7 1.5 P i (MW).7. 3..1.9.8 P e (MW).1 1.8 1.8 3.8 1.7 3.8 th τ E (s).89.18.161.1.15.15 τ m (s).76.19.118.16.1.7 and low T e cases of Fig. 1. The internal disruption, or sawtooth instability, is suppressed in these plasmas using NBI during the current ramp to broaden the current profile and keep the central safety factor above unity; this simplifies the transport analysis near the plasma center where T i and T e differ the most. Figure shows that the ion thermal diffusivity increases with increasing electron temperature like χ i T e for these plasmas; this strong dependence indicates that the ion heat transport is sensitive to T e in this regime. This sensitivity is likely due to the destabilization of the ITG mode, as discussed later in this Letter. The electron thermal diffusivity also tends to increase for higher T e but in a more GENERAL ATOMICS REPORT GA A311 3

DEPENDENCE OF HEAT AND PARTICLE TRANSPORT Petty et al. 5 χ high Te / χ low Te 3 1. Helium Particle Ion heat Electron heat...6.8 1. Fig.. Ratio of electron and ion thermal diffusivities and helium particle diffusivity for the T e scan at fixed T i shown in Fig. 1. The lined shading indicates the standard deviation of the random error. complicated manner than the ions, perhaps indicating that χ e depends upon both T e and T e. Figure also shows that the helium particle transport increases with increasing T e by an amount that is between the χ i and χ e dependences. The helium particle transport cannot be determined in the outer regions of the plasma because the evolution is too rapid. In the second experiment, the ion temperature is varied at nearly constant electron temperature, as shown in Fig. 3, and it is found that confinement increases with increasing T i. This is the opposite trend as found for the T e scan. The ion temperature is varied by % by increasing the NBI power and decreasing the ECH and fast wave power at fixed density, as shown in column (b) of Table I. Since the thermal energy confinement time in this case increases with increasing ion temperature like τ E th Ti.±., a higher value of β is achieved for the plasma with higher T i / T e despite less total heating power. A local transport analysis confirms these results. In Fig., the electron thermal diffusivity is seen to decrease with increasing ion temperature approximately like χ e T ī, demonstrating that the electron heat transport is sensitive to T i in this regime. The ion thermal diffusivity also decreases with increasing T i in Fig., although this dependence is more complicated to interpret since both T i and T i are varying. The positive reinforcement between χ i and T i likely contributes to forming the favorable hot ion mode of confinement [1 5]. GENERAL ATOMICS REPORT GA A311

Petty et al. DEPENDENCE OF HEAT AND PARTICLE TRANSPORT 8 (a) 8 (b) 6 6 T e (kev)....6 T i (kev).8 1.....6.8 1. Fig. 3. Radial profiles of (a) electron temperature, and (b) ion temperature for the T i scan at fixed T e given in column (b) of Table I. 1..8 χ high Ti / χ low Ti.6.... Ion heat Electron heat...6.8 1. Fig. Ratio of electron and ion thermal diffusivities for the T i scan at fixed T e shown in Fig. 3. GENERAL ATOMICS REPORT GA A311 5

DEPENDENCE OF HEAT AND PARTICLE TRANSPORT Petty et al. In the third experiment, the ratio of the ion and electron temperatures is varied at fixed plasma pressure, as seen in Fig. 5, and shows that transport is dependent upon how the plasma stored energy is divided between the electron and ion fluids. This can be considered to be a non-dimensional transport experiment, where the dimensionless parameter T i / T e is varied at fixed β, safety factor, Z eff, etc. For a % scan in T i / T e, column (c) of Table I shows that the thermal energy confinement time increases with increasing ion to electron temperature ratio like τ E th ( Ti / T e ).1±., which agrees with the results from the first two experiments in Table I. The local heat transport dependence on T i / T e, shown in Fig. 6, is also consistent with the transport dependences on T e and T i shown in Figs. and, with both the electron and ion thermal diffusivities decreasing for higher T i / T e. (Since T e, T e, T i, and T i are all varying in this case, only the scalings with the volume averaged temperatures are indicated in Fig. 6 for simplicity.) Figure 6 also shows that the helium particle diffusivity decreases with increasing T i / T e by an amount that is similar to the electron thermal diffusivity. (a) 6 (b) 1 T i / T e β (%)....6.8 1.....6.8 1. Fig. 5. Radial profiles of (a) ratio of ion and electron temperatures, and (b) thermal beta for the T i / T e scan at fixed β given in column (c) of Table I. The momentum confinement times ( τ m ) given in Table I also increase with increasing T i / T e, similar to the energy confinement results. A regression analysis of this dependence over all discharges shows that τ m T i / T e 3. Thus, the plasma rotation slows down with the application of ECH and fast wave heating, which in turn causes the measured E B shearing rate to vary by as much as 3% in the outer half of the plasma. (We note that the computed E B shearing rate obtained from the experimental toroidal velocity profile and the calculated poloidal velocity profile from neoclassical theory differs from the measured E B shearing rate by as much as a factor of and exhibits the wrong radial shape.) Since E B 6 GENERAL ATOMICS REPORT GA A311

Petty et al. DEPENDENCE OF HEAT AND PARTICLE TRANSPORT 1. χ high Ti / T e / χ low Ti / T e.8.6.... Helium Particle Electron heat Ion heat...6.8 1. Fig. 6. Ratio of electron and ion thermal diffusivities and helium particle diffusivity for the T i / T e scan at fixed β shown in Fig. 5. shear can reduce the heat and particle transport by connecting unstable modes to stable modes [1], the sensitivity of the transport results to variations in the E B shear warrants examination. Simulations using the gyro-landau-fluid GLF3 drift wave transport model [11] in the MLT code [1] show that while the E B shear is acting to reduce the overall level of transport, the differences in the E B shear within the T i / T e scan has a negligible effect on the predicted temperature profiles. The sensitivity of the heat and particle transport to the ratio of the ion and electron temperatures is likely due to the destabilization of the ITG mode (the electron temperature gradient mode is predicted to be stable). Modeling of these H mode plasmas using the GLF3 transport model shows that the measured T i profile in this regime is close to marginal stability for the ITG mode. Since the critical ion temperature gradient for the onset of this mode increases linearly with increasing T i / T e, an increase in T e at fixed T i will increase the ITG driven heat and particle transport. Conversely, an increase in T i at fixed T e (and fixed T i ) will cause a reduction in the ITG driven transport. The sensitivity of the measured heat and particle transport to T i / T e can be explained by the large incremental diffusivity of the ITG mode, which tends to pin the ion temperature gradient to the critical value. Figure 7(a) shows the scaling of the predicted thermal diffusivities for the T e scan at fixed T i (Figs. 1 and ) using the GLF3 model. In the simulation, the measured density and rotation profiles are utilized and the T i and T e profiles are calculated using the radial heat GENERAL ATOMICS REPORT GA A311 7

DEPENDENCE OF HEAT AND PARTICLE TRANSPORT Petty et al. fluxes obtained from a power balance analysis. The GLF3 model predicts a similar sensitivity of transport to T i / T e as is observed experimentally, with the theoretical thermal diffusivities in Fig. 7(a) increasing by nearly the same amount as found in the experiment; the particle diffusivity has a similar T i / T e dependence. The strong T i / T e dependence of transport in the GLF3 model for the T e scan at fixed T i is better seen in Fig. 7(b), which shows that χ i (T i / T e ) 3. and χ e (T i / T e ). around the experimental point. Figure 7(b) also shows that the ITG driven transport becomes greatly suppressed for T i / T e >. (a) 3 Ion Electron χ high / T e / χ low / T e 1. χ (m / s) 1 Exp (b) 5 1 3 Ti / T e...6.8 1. Fig. 7. (a) Predicted ratio of electron and ion thermal diffusivities, and (b) predicted dependence of χ i and χ e on the ion to electron temperature ratio at r / a =. from the GLF3 model for the T e scan at fixed T i shown in Fig.. The location of the experimental point is also indicated in (b). In conclusion, experiments in ELMing H mode plasmas on the DIII D tokamak have measured the dependence of cross-magnetic-field transport on the ratio of the ion and electron temperatures and show a strong temperature coupling effect between the ion and electron fluids. The electron and ion thermal diffusivities, the helium particle diffusivity, and the momentum transport all decrease with increasing T i / T e, regardless of which temperature is being varied. The sensitivity of confinement to changes in the ion to electron temperature ratio, τ E th (Ti / T e ), is likely explained by the destabilization of the ITG mode near threshold given the linear T i / T e dependence of the critical ion temperature gradient. Since future ignition devices will also likely have T i profiles close to marginal stability, these 8 GENERAL ATOMICS REPORT GA A311

Petty et al. DEPENDENCE OF HEAT AND PARTICLE TRANSPORT results show that confinement can be significantly improved in such devices by operating in a slight hot ion mode ( T i 1. T e ) [13]. The authors would like to thank J.S. degrassie, E.A. Lazarus, J. Lohr, F.W. Baity, and R.I. Pinsker for operating the tokamak and radiofrequency heating systems for these experiments. This work is supported by the U.S. Department of Energy under Contracts DE-AC3-99ER563 and DE-AC5-96OR6 and Grant DE-FG3-9ER511. References [1] K.H. Burrell et al., in Plasma Physics and Controlled Nuclear Fusion Research, 199, Washington, DC (IAEA, Vienna, 1991), Vol. 1, p. 13. [] G.L. Jackson et al., Phys. Rev. Lett. 67, 398 (1991). [3] J.D. Strachan at al., Phys. Rev. Lett. 58, 1 (1987). [] F.M. Levinton et al., Phys. Rev. Lett. 75, 17 (1995). [5] E.J. Strait et al., Phys. Rev. Lett. 75, 1 (1995). [6] J.L. Luxon and L.G. Davis, Fusion Technol. 8, 1 (1985). [7] C.C. Petty et al., Phys. Rev. Lett. 69, 89 (199). [8] H. St. John et al., in Plasma Physics and Controlled Nuclear Fusion Research, 199, Seville (IAEA, Vienna, 1995), Vol. 3, p. 63. [9] M.R. Wade et al., Phys. Plasmas, 357 (1995). [1] R.E. Waltz, R.L. Dewar, and X. Garbet, Phys. Plasmas 5, 178 (1998). [11] R.E. Waltz et al., Phys. Plasmas, 8 (1997). [1] J.A. Konings and R.E. Waltz, Nucl. Fusion 37, 863 (1997). [13] J.F. Clarke, Nucl. Fusion 5, 563 (198). GENERAL ATOMICS REPORT GA A311 9