ABSTRACT, POSTER LP1 12 THURSDAY 11/7/2001, APS DPP CONFERENCE, LONG BEACH. Recent Results from the Quiescent Double Barrier Regime on DIII-D
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1 ABSTRACT, POSTER LP1 1 THURSDAY 11/7/1, APS DPP CONFERENCE, LONG BEACH Recent Results from the Quiescent Double Barrier Regime on DIII-D E.J. Doyle, K.H. Burrell, T. Casper, J.C. DeBoo, A. Garofalo, P. Gohil, C.M. Greenfield, R.J. Groebner, J. Kinsey, L.L. Lao, C.J. Lasnier, M. Makowski, G.L. McKe e, R.A. Moyer, G. Porter, T.L. Rhodes, G.M. Staebler, B.W. Stallard, G. Wang, W.P. West, L. Zeng and the DIII-D Team, DIII-D National Fusion Facility, San Diego, California The Quiescent Double Barrier (QDB) regime combines internal transport barriers with a quiescent, ELM-free H-mode edge ( QH-mode), yielding sustained, high performance plasmas. In the QH-mode edge, benign MHD activity, usually in the form of an Edge Harmonic Oscillation (EHO), provides density and radiated power control In recent experiments, physics understanding of the mechanisms leading to the formation of the QDB plasmas has been improved, and both absolute (β 3.8%, S n s 1 ) and relative (β N H 89 =7 for 1τ E ) pe rformance increased A signature of operation with a QH mode edge appears to be very large radial electric fields in the edge and SOL. In the plasma core, simulations and m odeling replicate many of the features of the observed transport and fluctuation behavior, including the ion temperature profile and turbulence correlation lengths. Slow high-z impurity accumulation (τ 5 ms) is observed in the center of many QDB plasmas, and is the subject of ongoing analysis. EJD APS1 1/31/1 1
2 OVERVIEW Introduction What is the Quiescent Double Barrier (QDB) regime? The Quiescent H-mode (QH-mode) edge Detailed characteristics and conditions required for QH-mode operation Edge Harmonic Oscillation (EHO) Divertor and SOL conditions Quiescent Double Barrier (QDB) operation Core transport and fluctuations Impurity issues Density peaking Summary EJD APS1 1/31/1
3 SOME NEW ACRONYMS QH-mode: Quiescent H-mode An ELM-free H-mode with density and radiated power control QDB: Quiescent Double Barrier Operation with an internal transport barrier (ITB) inside a QH-mode edge EHO: Edge Harmonic Oscillation A continuous MHD mode usually associated with QH-mode operation EJD APS1 1/31/1 3
4 SUSTAINED ELM-FREE H-MODE OPERATING REGIME OBTAINED WITH DENSITY AND RADIATED POWER CONTROL Plasma Current (MA) D α NBI Power (MW) Radiated Power (MW) ELM-free, QH-mode Edge Time (s) β N *H Time (s) Maintains quiescent ELM-free edge for >3.5 s, ~5τ E Central Density (1 19 m 3 ) Line Average Density (1 19 m 3 ) (6) B amplitude (a.u.). 5. EJD APS1 1/31/1
5 QDB REGIME COMBINES CORE TRANSPORT BARRIER WITH QUIESCENT EDGE BARRIER QUIESCENT DOUBLE BARRIER Edge pedestal elevates central temperatures, improving fusion performance kev q 5 3 ITB + L-mode edge L-mode ITB QDB T i QH-mode edge QDB s L mode+itb s L-mode s ρ kev 1 19 m ITB + L-mode edge L-mode ITB QDB T e n e QH-mode edge QH-mode edge ρ EJD APS1 1/31/1 5
6 WHAT IS THE SIGNIFICANCE OF QDB OPERATION? H-mode is the operating regime of choice for next-step devices, but has nonoptimal features due to the impact of Edge Localized Modes (ELMs) Pulsed heat loads to the divertor can cause rapid erosion Type I (Giant) ELMs can inhibit or destroy the ITBs desired for advanced tokamak (AT) scenarios Double barriers have been achieved on JT-6U and JET ELMs can couple to core MHD modes, limiting beta and performance QDB plasmas address these issues: Provides high quality ELM-free H-mode with density and radiated power control The QH-mode edge is compatible with ITBs Demonstrated long pulse, high performance capability: >3.5 s or 5 τ E achieved, limited only by beam pulse duration β N H 89 =7 for 1 τ E EJD APS1 1/31/1 6
7 CONDITIONS REQUIRED FOR QH-MODE/QDB OPERATION Key operational conditions to obtain the QH-mode edge are: Neutral beam injection counter to the plasma current (counter-nbi), at power levels.5 MW (higher power at higher current) Divertor pumping to reduce the edge density and neutral pressure A gap between the plasma edge and the outer wall (low toroidal field side) of ~1 cm QH-mode has been obtained with Both lower and upper single-null discharges.67 I p (MA) 1.6 and.95 B T (T).1 Most work done at 1. I p (MA) 1.6 and 1.8 B T (T).1 With triangularity δ of and q of Obtaining an ITB inside the QH-mode edge to form a QDB plasma is straightforward using conventional ITB formation techniques EJD APS1 1/31/1 7
8 QUIESCENT H-MODE (QH-MODE) EDGE Issues addressed in this section include: Operational conditions required to obtain QH-mode Edge and divertor conditions Density and radiated power control is provided by an edge harmonic oscillation (EHO), which generates particle transport Characteristics of the EHO Is the EHO really an edge mode? EJD APS1 1/31/1 8
9 THE PLASMA EDGE DURING THE QUIESCENT PHASE IS AN H-MODE EDGE Edge gradients in quiescent phase are comparable to those in ELMing phase Note high T i pedestal QH-mode edge also has other standard H-mode signatures Edge E r well Reduced turbulence EJD APS1 1/31/1 9
10 QH-MODE PLASMAS HAVE LARGE EDGE RADIAL ELECTRIC FIELD, E r E r (kv/m) CER data show large E r in SOL and very deep E r well inside separatrix ELM-free (co-nbi) QH-mode (counter-nbi) s s CER Data Separatrix.5 R (m).3 Langmuir probe data also show large E r in SOL SOL E r is at normal levels in ELMing counter- NBI discharge Change is associated with QH-mode, not counter-nbi per se E r (kv/m) QH-mode (counter-nbi) ELMing H-mode (counter-nbi) Separatrix Langmuir Probe Data R (m) s s EJD APS1 1/31/1 1
11 Q H-MODE EDGE HAS LOWER DENSITY AND HIGHER TEMPERATURE THAN CONVENTIONAL ELMING H-MODE. QH-MODE PED T e (kev) / n GW 1. ELM PHASE IN QH-MODE SHOT, LAST % OF ELM CYCLE TYPE III TYPE I, LAST % OF ELM CYCLE δ >.3 UPPER PED n e (1 m -3 ) / n GW EJD APS1 1/31/1 11
12 QDB OPERATION HAS MODERATE HEAT FLUX TO THE DIVERTOR TARGET PLATES P floor (MW/m ) Baffle nose Outer strike point H-mode.5 MW, 8x1 19 m -3 H-mode 6.5 MW, 3.6x1 19 m -3 QDB 7 MW,.x1 19 m R (m) Note that present-day devices can match anticipated core or edge reactor conditions, but not both Reactor relevant core plasmas in present-day devices may have non-optimal divertor conditions EJD APS1 1/31/1 1
13 QDB OPERATION HAS SIGNIFICANT HEAT FLUX TO THE BAFFLE PLATE, 3- MIDPLANE CM OUTSIDE SEPARATRIX Langmuir probe IRTV heat flux OSP. MW/m. MW/m T i (kev) ms Shot ms CER T i Particle flux (A/cm^) R=168.6 cm Time (ms) ρ Heat flux, hot ions and particle flux all observed 3- midplane cm outside sepratrix during EHO (see Lasnier, LP1 36, this session) Heat flux to baffle plate is consistent with midplane SOL T i measurements Bdot (Gauss/s) (Photons/ cm^/sr/s) Ḃ Langmuir probe particle flux D α emission EJD APS1 1/31/1 13
14 QUIESCENT OPERATION IS USUALLY ASSOCIATED WITH THE PRESENCE OF AN EDGE HARMONIC OSCILLATION (EHO) EHO is seen on magnetic, density and electron temperature fluctuation diagnostics during QH-mode operation Quiescent operation also obtained with a global 1/1 mode (single example) Toroidal mode mixture (amplitude and harmonic content) can change spontaneously Edge profiles, density and impurity control not sensitive to mode mixture Color contour plot of B θ signal Frequency (khz) n= n=3 n= n= Time (s) EJD APS1 1/31/1 1
15 Frequency (khz) THE EHO CAUSES PARTICLE TRANSPORT EHO MODULATES BOTH PARTICLE FLUX TO DIVERTOR AND SOL DENSITY PROFILE Divertor Langmuir probe I sat signal shows particle flux is modulated at EHO frequencies EHO harmonics account for ~1% of the total flux to the probe Contour plot of divertor Langmuir probe Isat Time (s).. Intensity scale (a.u) Major Radius (m) High resolution profile reflectometer system shows scrape-off layer (SOL) density profile is modulated at EHO frequency ~ n e (a.u.) from.8x1 18 m -3 density layer 15 GHz fixed frequency reflectometer Contour plot of location of SOL density layers as function of time Separatrix (a) (b) Time (ms) n e (1 18 m -3 ) EJD APS1 1/31/1 15
16 THE EDGE HARMONIC OSCILLATION (EHO) IS LOCATED AT THE BASE OF THE EDGE PEDESTALS High resolution measurements with Beam Emission Spectroscopy (BES) and profile reflectometer systems indicate that the EHO is located at the base of the edge profile pedestals, at or slightly outside the separatrix (see Burrell, ROP1 17, Thursday) Reflectometer data (1) BES data () δne (a.u.) n e (1 18 m -3 ) Edge density profile Separatrix n e (1 18 m -3 ) Density fluctuation associated with EHO 1696 Thomson Reflectometer Separatrix Major Radius (m) T e (kev) T i (kev) E r (kv/m) Major Radius (m). BES ñ (a.u.) Separatrix..5 R (m).3 EJD APS1 1/31/1 16
17 CHARACTERISTICS OF THE EHO ON DIII-D AND COMPARISON TO THE ELM-FREE EDA H MODE ON C-MOD Edge Harmonic Oscillation () Quasi-Coherent Mode (C MOD) Increase Dα level in divertor Yes Yes Increase particle transport Yes Yes across separatrix Location Foot of edge barrier Edge density barrier Frequency 6 1 khz (n=1) 6 khz Frequency spread..5. f (FWHM)/f Toroidal mode number Multiple, variable mix n=1 1 Unknown Poloidal wavelength ~1 cm (m~5) ~1 cm Edge ion collisionality Collisionless Collisional Different edge modes on two different machines both generate ELM-free H-mode operation EJD APS1 1/31/1 17
18 QUIESCENT DOUBLE-BARRIER (QDB) OPERATION Issues addressed in this section include: Performance obtained in QDB regime Transport and fluctuation analysis and modeling Impurity issues High-Z impurities accumulate Ways to address density peaking EJD APS1 1/31/1 18
19 COMBINATION OF CORE ITB AND QH-MODE EDGE RESULTS IN SUSTAINED HIGH PERFORMANCE β N H 89 =7 for 1 τ E (1.6 s) Example of quiescent operation without EHO, but with global 1/1 mode Same performance obtained in discharges with EHO Plasma Current (MA) D α Central Density (1 19 m 3 ) Line Average Density (1 19 m 3 ) ELM-free, QH-mode Edge Time (s) β N *H 89 Neutron rate (1 15 s 1 ) NBI Power (MW) Radiated Power (MW) (7) Time (s) EJD APS1 1/31/1 19
20 TRANSPORT ANALYSIS CONFIRMS PRESENCE OF DOUBLE (CORE AND EDGE) TRANSPORT BARRIERS 1 χ i ITB χ e ITB L-mode ITB + L-mode edge m /s 1. QDB χneo i ρ Core transport is similar to that in ITB plasmas with an L-mode edge ITB refers to region of reduced transport relative to L-mode Edge transport is typical of H-mode QDB s L mode+itb s L-mode s Core and edge barriers are kept separate by region of low ExB shear ρ EJD APS1 1/31/1
21 SIMULATIONS USING THE GLF3 MODEL REPRODUCE THE QDB CORE ION BARRIER (see Kinsey, QO1 1, Thursday) T (kev) s T e T i Data Model Data Model γ / (c s /a) γ max γ (ExB shearing E rate) ρ Steady-state simulation reproduces core ion temperature barrier Core T e profile not accurately reproduced Prediction is that core turbulence is not completely suppressed Turbulence growth rate and ExB shear in approximate balance GKS code makes similar prediction ρ EJD APS1 1/31/1 1
22 CORE BARRIER EXISTS WITHOUT COMPLETE TURBULENCE SUPPRESSION, IN AGREEMENT WITH GLF3 MODELING Internal broadband turbulence is not completely suppressed as the QDB core barrier evolves (see Zeng, LP1 16, this session) Residual turbulence still significantly above the FIR scattering system detection limit Contrasts with typical ITB in, where core turbulence is suppressed to the noise floor High frequency coherent core modes are often detected. Reflectometer data indicate these modes are localized to ρ~-.. Frequency (khz) NBI initiation. ñ (a.u.) FIR scattering 171 k = 1 cm -1 Time (s) } 1.5 s.5 s 3.5 s Core localized quasi-coherent modes Edge modes. System noise floor f (khz) EJD APS1 1/31/1
23 STEP SIZE FOR CORE TURBULENT TRANSPORT IS REDUCED IN QDB PLASMAS In L-mode, correlation lengths are observed to scale approximately as 5-1ρ s 8 6 (a) L-mode data set Correlation length, r 5 1 ρ s In QDB plasmas, core correlation lengths are significantly lower than the scaling observed in L-mode 8 6 (b) QDB data set Correlation length, r 5 1 ρ s Initial theory-based modeling using the UCAN global gyrokinetic code tracks core experimental trends and magnitude ITG turbulence in circular geometry 8 6 Simulations Correlation length, r 5 1 ρ s cm cm cm ρ ρ ρ EJD APS1 1/31/1 3
24 HIGH-Z IMPURITY ACCUMULATION IS AN ISSUE FOR LONG PULSE QDB DISCHARGES (West, invited talk KI1 ) D α Ni XXVI (1 15 ph/cm a /s) Ni XXV (1 15 ph/cm /s) NBI Power (MW) Radiated Power (MW) ELM-free, QH-mode Edge Central Density (1 19 m 3 ) Line Average Density (1 19 m 3 ) Central Carbon Fraction (%) Time (s) Nickel content increases with time, but contribution to radiated power is low, <.3 MW Low-Z impurities, e.g. carbon, stay approximately constant EJD APS1 1/31/1
25 Pinch Velocity (m/s) MEASURED IMPURITY TRANSPORT LARGER THAN NEOCLASSICAL FROM.1<ρ<.5 Experimental D and v obtained from time dependence of measured impurity density profiles (from CER system) Neoclassical transport coefficients obtained from the NCLASS code Impurity transport is anomalous where measured χ i is near neoclassical Measured neon profile is significantly less peaked than predicted by neoclassical transport rates V He (meas) V He (neoc) V Ne (meas) V Ne (neoc) ρ Diffusivity (m /s) D He (meas) D He (neoc) D Ne (meas) (neoc) D Ne... ρ Density Profile (au) n Ne Profile Expected from Measured D Ne and V Ne Profile Expected from Neoclassical D and V Ne Ne ρ EJD APS1 1/31/1 5
26 REDUCED DENSITY PEAKING IS REQUIRED FOR INCREASED PERFORMANCE - SEVERAL CONTROL TOOLS EXIST Advantages of reduced density peaking include: Reduced central high-z impurity accumulation Improved bootstrap current alignment Control tools have (transiently) demonstrated ability to reduce density peaking (Gohil, LP1, this session): Near on-axis ECH Increased triangularity Off-axis pellet injection Impurity puffing Example shown is of density change with increased lower triangularity δ LOW n e (o)/n AVE decreases from. to δ up Central Density (1 19 m 3 ) Te ped (kev) Max. P e (kpa/m) Divertor D α (a.u.) δ low Line Average Density (1 19 m 3 ) Pedestal Density (1 19 m 3 ) Time (s) EJD APS1 1/31/1 6
27 ON-AXIS ECH REDUCES THE CENTRAL DENSITY AND DENSITY PEAKING, WITH LITTLE EFFECT ON PERFORMANCE Electron density profile becomes broader and central density is reduced Nickel XXVI emission is reduced, analysis required to determine if this is decrease in impurity content P ECH ~ MW, ρ ECH ~.1 n e (o)/n AVE decreases from.6 to 1.7 n e (1 19 m 3 ) Before ECH ms after ECH start ms after ECH start (kev) (MW) (kev) ( 1 15 s 1 ) ( 1 3 ms 1 ) T i at several radii C VI rotation at several radii Neutron rate T e () ECH power ρ 36 8 Time EJD APS1 1/31/1 7
28 ADVANCED TOKAMAK ISSUES FOR THE QDB REGIME Advanced Tokamak (AT) research seeks to produce a steady-state high performance regime QDB appears to be an excellent target for sustainment using ECCD [Casper, et al., poster FP1.8, Tue. AM] Barriers to AT applications of the QDB regime: Counter-NBI Balanced NBI (no momentum input) should be similar to counter for formation of separate barriers (both have pressure dominated E r ) Role of counter-nbi still unknown for EHO dominated edge Counter-NBCD is small but significant; needs to be overcome by current drive Peaked density profile: Associated peaked pressure profile limits attainable plasma β. Narrow bootstrap current profile not optimal for steady-state sustainment. Neoclassical impurity transport leads to retention of high-z impurities. Near-term studies of the QDB will focus on methods of broadening the density profile. EJD APS1 1/31/1 8
29 CONCLUSIONS QDB results demonstrate that it is possible to have sustained, high quality H-mode performance with an ELM-free edge, with density and radiated power control Addresses major issue in Fusion research, ELM induced pulsed divertor heat loads The QDB regime contains compatible core and edge transport barriers QH-mode is normally associated with a continuous edge harmonic oscillation (EHO), which provides increased particle transport Turbulence and transport behavior of QDB discharges is reproduced by initial simulations and modeling QDB regime has demonstrated long pulse, high performance capability >3.5 s or 5 τ E achieved, limited only by beam pulse duration β N H 89 =7 for 1 τ E Impurity accumulation is an issue. Control tools are available (shaping, ECH, pellets) to reduce density peaking and core impurity accumulation EJD APS1 1/31/1 9
30 FOR MORE INFORMATION RELATED TO THE QUIESCENT DOUBLE BARRIER REGIME Invited talks, Wednesday and Friday KI1.: W.P. West, Energy, Impurity and Particle Transport in Quiescent Double Barrier Discharges in. Poster this afternoon. UI1.5: T.L. Rhodes, Comparison of Turbulence Measurements From DIII-D L-mode and High Performance Plasmas to Turbulence Simulations and Models. Poster, Tuesday morning FP1.8: T.A. Casper, Predictive Modeling of Tokamak Configurations. Contributed oral, Tuesday morning FO1.1: C.M. Greenfield, et al., "The Quiescent Double Barrier Regime in DIII-D." Posters, Wednesday afternoon LP1.: P. Gohil, et al., Development of Methods to Control Internal Transport Barriers in DIII-D Plasmas. LP1.16: L. Zeng, et al., Fluctuation Characteristics of the QDB Regime in DIII- D. LP1.36: C.J. Lasnier, et al., Scrape-off Layer Characteristics of QH and QDB Plasma Compared with ELMing H-mode and Advanced Tokamak Plasma. Contributed oral, Thursday morning QO1.1: J.E. Kinsey, et al., Progress in Modeling Internal Transport Barrier Formation Using the GLF3 Transport Model. Poster, Thursday afternoon RP1.17: K.H. Burrell, et al., Physics of the Edge Harmonic Oscillation in Quiescent H-Mode Discharges in DIII- D. EJD APS1 1/31/1 3
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