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

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

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

Transcription

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

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

DIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN Presented by C.M. GREENFIELD for J.C. DeBOO, T.C. LUCE, B.W. STALLARD, E.J. SYNAKOWSKI, L.R. BAYLOR,3 K.H. BURRELL, T.A. CASPER, E.J.

More information

Characteristics of the H-mode H and Extrapolation to ITER

Characteristics of the H-mode H and Extrapolation to ITER Characteristics of the H-mode H Pedestal and Extrapolation to ITER The H-mode Pedestal Study Group of the International Tokamak Physics Activity presented by T.Osborne 19th IAEA Fusion Energy Conference

More information

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

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 16th IAEA Fusion Conference

More information

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

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team* ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 38th APS/DPP Meeting NOVEMBER 11 15, 1996 Denver, Colorado

More information

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

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas EX/P5-35 L. Schmitz 1), A.E. White 1), G. Wang 1), J.C. DeBoo 2),

More information

INTERNAL TRANSPORT BARRIERS WITH

INTERNAL TRANSPORT BARRIERS WITH INTERNAL TRANSPORT BARRIERS WITH COUNTER-NEUTRAL BEAM INJECTION IN C.M. GREENFIELD, E.J. SYNAKOWSKI, K.H. BURRELL, M.E. AUSTIN, D.R. BAKER, L.R. BAYLOR, T.A. CASPER, J.C. DeBOO, E.J. DOYLE, D. ERNST, J.R.

More information

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

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas by T.M. Wilks 1 with A. Garofalo 2, K.H. Burrell 2, Xi. Chen 2, P.H. Diamond 3, Z.B. Guo 3, X. Xu

More information

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

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE T.H. Osborne 1, P.B. Snyder 1, R.J. Groebner 1, A.W. Leonard 1, M.E. Fenstermacher 2, and the DIII-D Group 47 th Annual Meeting

More information

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

Particle transport results from collisionality scans and perturbative experiments on DIII-D 1 EX/P3-26 Particle transport results from collisionality scans and perturbative experiments on DIII-D E.J. Doyle 1), L. Zeng 1), G.M. Staebler 2), T.E. Evans 2), T.C. Luce 2), G.R. McKee 3), S. Mordijck

More information

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D GA A443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D by R.J. GROEBNER, T.N. CARLSTROM, K.H. BURRELL, S. CODA, E.J. DOYLE, P. GOHIL, K.W. KIM, Q. PENG, R. MAINGI, R.A. MOYER, C.L. RETTIG, T.L. RHODES,

More information

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Transport Improvement Near Low Order Rational q Surfaces in DIII D Transport Improvement Near Low Order Rational q Surfaces in DIII D M.E. Austin 1 With K.H. Burrell 2, R.E. Waltz 2, K.W. Gentle 1, E.J. Doyle 8, P. Gohil 2, C.M. Greenfield 2, R.J. Groebner 2, W.W. Heidbrink

More information

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

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* E. Marmar, B. Lipschultz, A. Dominguez, M. Greenwald, N. Howard, A. Hubbard, J. Hughes, B. LaBombard, R. McDermott, M. Reinke,

More information

ELMs and Constraints on the H-Mode Pedestal:

ELMs and Constraints on the H-Mode Pedestal: ELMs and Constraints on the H-Mode Pedestal: A Model Based on Peeling-Ballooning Modes P.B. Snyder, 1 H.R. Wilson, 2 J.R. Ferron, 1 L.L. Lao, 1 A.W. Leonard, 1 D. Mossessian, 3 M. Murakami, 4 T.H. Osborne,

More information

1999 RESEARCH SUMMARY

1999 RESEARCH SUMMARY 1999 RESEARCH SUMMARY by S.L. Allen Presented to DIII D Program Advisory Committee Meeting January 2 21, 2 DIII D NATIONAL FUSION FACILITY SAN DIEGO 3 /SLA/wj Overview of Physics Results from the 1999

More information

C-Mod Transport Program

C-Mod Transport Program C-Mod Transport Program PAC 2006 Presented by Martin Greenwald MIT Plasma Science & Fusion Center 1/26/2006 Introduction Programmatic Focus Transport is a broad topic so where do we focus? Where C-Mod

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK

More information

DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS

DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS GA A23775 DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS by P. GOHIL NOVEMBER 2001 QTYUIOP DISCLAIMER This report was prepared as

More information

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

GA A23428 IMPROVEMENT OF CORE BARRIERS WITH ECH AND COUNTER-NBI IN DIII D GA A348 IMPROVEMENT OF CORE BARRIERS WITH ECH by C.M. GREENFIELD, K.H. BURRELL, T.A. CASPER, J.C. DeBOO, E.J. DOYLE, P. GOHIL, R.J. GROEBNER, J.E. KINSEY, J. LOHR, M. MAKOWSKI, G.R. McKEE, M. MURAKAMI,

More information

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

Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D L. Schmitz1 with C. Holland2, T.L. Rhodes1, G. Wang1, J.C. Hillesheim1, A.E. White3, W. A. Peebles1, J. DeBoo4, G.R. McKee5, J. DeGrassie4,

More information

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

Pedestals and Fluctuations in C-Mod Enhanced D α H-modes Pedestals and Fluctuations in Enhanced D α H-modes Presented by A.E.Hubbard With Contributions from R.L. Boivin, B.A. Carreras 1, S. Gangadhara, R. Granetz, M. Greenwald, J. Hughes, I. Hutchinson, J. Irby,

More information

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

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of

More information

Progress Toward High Performance Steady-State Operation in DIII D

Progress Toward High Performance Steady-State Operation in DIII D Progress Toward High Performance Steady-State Operation in DIII D by C.M. Greenfield 1 for M. Murakami, 2 A.M. Garofalo, 3 J.R. Ferron, 1 T.C. Luce, 1 M.R. Wade, 1 E.J. Doyle, 4 T.A. Casper, 5 R.J. Jayakumar,

More information

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

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D by J.S. degrassie, D.R. BAKER, K.H. BURRELL, C.M. GREENFIELD, H. IKEZI, Y.R. LIN-LIU, C.C. PETTY, and R. PRATER APRIL 1997 This report

More information

UCLA. Broadband Magnetic and Density Fluctuation Evolution Prior to First ELM in DIII-D Edge Pedestal. Presented by G. Wang a, In collaboration with

UCLA. Broadband Magnetic and Density Fluctuation Evolution Prior to First ELM in DIII-D Edge Pedestal. Presented by G. Wang a, In collaboration with Broadband Magnetic and Density Fluctuation Evolution Prior to First ELM in DIII-D Edge Pedestal Presented by G. Wang a, In collaboration with W.A. Peebles a, P.B. Snyder b, T.L. Rhodes a, E.J. Doyle a,

More information

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald 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 OVERVIEW OF THE ALCATOR C-MOD PROGRAM IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OUTLINE C-Mod is compact, high field, high density, high power

More information

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

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER TRANSPORT PROGRAM C-Mod C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER C-MOD - OPPORTUNITIES AND CHALLENGES Prediction and control are the ultimate goals

More information

Edge Impurity Dynamics During an ELM Cycle in DIII D

Edge Impurity Dynamics During an ELM Cycle in DIII D Edge Impurity Dynamics During an ELM Cycle in by M.R. Wade 1 in collaboration with K.H. Burrell, A.W. Leonard, T.H. Osborne, P.B. Snyder, J.T. Hogan, 1 and D. Coster 3 1 Oak Ridge National Laboratory General

More information

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

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

More information

EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY*

EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY* EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY* by K.H. BURRELL Presented at the Transport Task Force Meeting Annapolis, Maryland April 3 6, 22 *Work supported by U.S. Department of Energy

More information

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

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant

More information

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES J. Mandrekas, W.M. Stacey Georgia Institute of Technology M. Murakami, M.R. Wade ORNL G. L. Jackson General Atomics Presented at the

More information

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges P.B. Snyder 1 Contributions from: H.R. Wilson 2, D.P. Brennan 1, K.H.

More information

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

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D by C.C. PETTY, P.A. POLITZER, R.J. JAYAKUMAR, T.C. LUCE, M.R. WADE, M.E. AUSTIN, D.P. BRENNAN, T.A. CASPER, M.S. CHU, J.C. DeBOO, E.J. DOYLE,

More information

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

Dependences of Critical Rotational Shear in DIII-D QH-mode Discharges Dependences of Critical Rotational Shear in DIII-D QH-mode Discharges by T.M. Wilks 1 with K.H. Burrell 2, Xi. Chen 2, A. Garofalo 2, R.J. Groebner 2, P. Diamond 3, Z. Guo 3, and J.W. Hughes 1 1 MIT 2

More information

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER

More information

Predicting the Rotation Profile in ITER

Predicting the Rotation Profile in ITER Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton

More information

Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations

Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations A.E. White,a) L. Schmitz,a) G.R. McKee,b) C. Holland,c) W.A. Peebles,a)

More information

THE ADVANCED TOKAMAK DIVERTOR

THE ADVANCED TOKAMAK DIVERTOR I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and

More information

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,

More information

Experimental test of the neoclassical theory of poloidal rotation

Experimental test of the neoclassical theory of poloidal rotation Experimental test of the neoclassical theory of poloidal rotation Presented by Wayne Solomon with contributions from K.H. Burrell, R. Andre, L.R. Baylor, R. Budny, P. Gohil, R.J. Groebner, C.T. Holcomb,

More information

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

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012 Impact of Torque and Rotation in High Fusion Performance Plasmas by W.M. Solomon 1 K.H. Burrell 2, R.J. Buttery 2, J.S.deGrassie 2, E.J. Doyle 3, A.M. Garofalo 2, G.L. Jackson 2, T.C. Luce 2, C.C. Petty

More information

THE DIII D PROGRAM THREE-YEAR PLAN

THE DIII D PROGRAM THREE-YEAR PLAN THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned

More information

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U EX/D-3 Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-6U N. Asakura ), H. Takenaga ), S. Sakurai ), G.D. Porter ), T.D. Rognlien ), M.E. Rensink ), O. Naito ), K. Shimizu

More information

DIII D Research in Support of ITER

DIII D Research in Support of ITER Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design

More information

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

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Z. Yan 1, G.R. McKee 1, J.A. Boedo 2, D.L. Rudakov 2, P.H. Diamond 2, G. Tynan 2, R.J. Fonck 1, R.J. Groebner 3, T.H. Osborne 3, and

More information

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. Lin-Liu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,

More information

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

Influence of Beta, Shape and Rotation on the H-mode Pedestal Height Influence of Beta, Shape and Rotation on the H-mode Pedestal Height by A.W. Leonard with R.J. Groebner, T.H. Osborne, and P.B. Snyder Presented at Forty-Ninth APS Meeting of the Division of Plasma Physics

More information

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Kenichi NAGAOKA 1,2), Hiromi TAKAHASHI 1,2), Kenji TANAKA 1), Masaki OSAKABE 1,2), Sadayoshi MURAKAMI

More information

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

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control P. A. Politzer, 1 A. W. Hyatt, 1 T. C. Luce, 1 F. W. Perkins, 4 R. Prater, 1 A. D. Turnbull, 1 D. P. Brennan, 5 J.

More information

Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.

Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0. Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0. Igor Bespamyatnov, William Rowan, Ronald Bravenec, and Kenneth Gentle The University of Texas at Austin,

More information

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

Observation of Neo-Classical Ion Pinch in the Electric Tokamak* 1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,

More information

TOKAMAK EXPERIMENTS - Summary -

TOKAMAK EXPERIMENTS - Summary - 17 th IAEA Fusion Energy Conference, Yokohama, October, 1998 TOKAMAK EXPERIMENTS - Summary - H. KISHIMOTO Japan Atomic Energy Research Institute 2-2 Uchisaiwai-Cho, Chiyoda-Ku, Tokyo, Japan 1. Introduction

More information

Understanding Edge Harmonic Oscillation Physics Using NIMROD

Understanding Edge Harmonic Oscillation Physics Using NIMROD Understanding Edge Harmonic Oscillation Physics Using NIMROD J. King With contributions from S. Kruger & A. Pankin (Tech-X); K. Burrell, A. Garofalo, R. Groebner & P. Snyder (General Atomics) Work supported

More information

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

Advances in the Physics Basis of the Hybrid Scenario on DIII-D Advances in the Physics Basis of the Hybrid Scenario on DIII-D C.C. Petty 1), W.P. West 1), J.C. DeBoo 1), E.J. Doyle 2), T.E. Evans 1), M.E. Fenstermacher 3), M. Groth 3), J.R. Ferron 1), G.R. McKee 4),

More information

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

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139 Alcator C-Mod Double Transport Barrier Plasmas in Alcator C-Mod J.E. Rice for the C-Mod Group MIT PSFC, Cambridge, MA 139 IAEA Lyon, Oct. 17, Outline Double Barrier Plasma Profiles and Modeling Conditions

More information

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:

More information

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D GA A25445 TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D by J.G. WATKINS, T.E. EVANS, C.J. LASNIER, R.A. MOYER, and D.L. RUDAKOV JUNE 2006 QTYUIOP DISCLAIMER This report was prepared

More information

Divertor Heat Flux Reduction and Detachment in NSTX

Divertor Heat Flux Reduction and Detachment in NSTX 1 EX/P4-28 Divertor Heat Flux Reduction and Detachment in NSTX V. A. Soukhanovskii 1), R. Maingi 2), R. Raman 3), R. E. Bell 4), C. Bush 2), R. Kaita 4), H. W. Kugel 4), C. J. Lasnier 1), B. P. LeBlanc

More information

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

Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence 1 Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence L. Schmitz, 1 C. Holland, 2 T.L. Rhodes, 1 G. Wang, 1 L. Zeng, 1 A.E. White,

More information

Scaling of divertor heat flux profile widths in DIII-D

Scaling of divertor heat flux profile widths in DIII-D 1 Scaling of divertor heat flux profile widths in DIII-D C.J. Lasnier 1, M.A. Makowski 1, J.A. Boedo 2, N.H. Brooks 3, D.N. Hill 1, A.W. Leonard 3, and J.G. Watkins 4 e-mail:lasnier@llnl.gov 1 Lawrence

More information

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D by E.J. DOYLE, J.C. DeBOO, T.A. CASPER, J.R. FERRON, R.J. GROEBNER, C.T. HOLCOMB, A.W. HYATT, G.L. JACKSON, R.J. LA HAYE, T.C. LUCE, G.R.

More information

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

SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-1 TOKAMAK PLASMAS V. Vershkov, L.G. Eliseev, S.A. Grashin. A.V. Melnikov, D.A. Shelukhin, S.V. Soldatov, A.O. Urazbaev and T-1 team

More information

Characteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas

Characteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas Characteristics of Internal Transport Barrier in JT-6U Reversed Shear Plasmas Y. Sakamoto, Y. Kamada, S. Ide, T. Fujita, H. Shirai, T. Takizuka, Y. Koide, T. Fukuda, T. Oikawa, T. Suzuki, K. Shinohara,

More information

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

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

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual

More information

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

CORE TURBULENCE AND TRANSPORT REDUCTION IN DIII-D DISCHARGES WITH WEAK OR NEGATIVE MAGNETIC SHEAR I JUL 2 5 m 7 GA-A22617 CORE TURBULENCE AND TRANSPORT REDUCTION IN DIII-D DISCHARGES WITH WEAK OR NEGATIVE MAGNETIC SHEAR by G.M. STAEBLER, C.M. GREENFIELD, D.P. SCHISSEL, K.H. BURRELL, T.A. CASPER, J.C.

More information

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

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas M.E. Fenstermacher, T.H. Osborne, T.W. Petrie, C.J. Lasnier, A.W. Leonard, J.G. Watkins, 3 T.N. Carlstrom,

More information

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

GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING by G.R. McKEE, C. HOLLAND, Z. YAN, E.J. DOYLE, T.C. LUCE, A. MARINONI, C.C. PETTY, T.L. RHODES, J.C. ROST, L. SCHMITZ, W.M. SOLOMON, B.J.

More information

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier EX/C-Rb Relationship between particle and heat transport in JT-U plasmas with internal transport barrier H. Takenaga ), S. Higashijima ), N. Oyama ), L. G. Bruskin ), Y. Koide ), S. Ide ), H. Shirai ),

More information

Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program

Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program OV/-5 Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program K.H. Burrell for the DIII D Team General Atomics, P.O. Box 8568, San Diego, California 986-568 email: burrell@fusion.gat.com

More information

Results From Initial Snowflake Divertor Physics Studies on DIII-D

Results From Initial Snowflake Divertor Physics Studies on DIII-D Results From Initial Snowflake Divertor Physics Studies on DIII-D S. L. Allen, V. A. Soukhanovskii, T.H. Osborne, E. Kolemen, J. Boedo, N. Brooks, M. Fenstermacher, R. Groebner, D. N. Hill, A. Hyatt, C.

More information

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

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model 1 THC/3-3 ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model J.E. Kinsey, G.M. Staebler, J. Candy, and R.E. Waltz General Atomics, P.O. Box 8608, San Diego, California

More information

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

ITB Transport Studies in Alcator C-Mod. Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co Transport Studies in Alcator C-Mod Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co With Contributions from: I. Bespamyatnov, P. T. Bonoli*, D. Ernst*, M.

More information

Rotation Speed Differences of Impurity Species in the DIII-D Tokamak and Comparison with Neoclassical Theory

Rotation Speed Differences of Impurity Species in the DIII-D Tokamak and Comparison with Neoclassical Theory Rotation Speed Differences of Impurity Species in the DIII-D Tokamak and Comparison with Neoclassical Theory L.R. Baylor, K.H. Burrell*, R.J. Groebner*, D.R. Ernst #, W.A. Houlberg, M. Murakami, and The

More information

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions P.B. Snyder 1, T.H. Osborne 1, M.N.A. Beurskens 2, K.H. Burrell 1, R.J. Groebner 1, J.W. Hughes 3, R. Maingi

More information

Progress in characterization of the H-mode pedestal

Progress in characterization of the H-mode pedestal Journal of Physics: Conference Series Progress in characterization of the H-mode pedestal To cite this article: A W Leonard 2008 J. Phys.: Conf. Ser. 123 012001 View the article online for updates and

More information

Theory Work in Support of C-Mod

Theory Work in Support of C-Mod Theory Work in Support of C-Mod 2/23/04 C-Mod PAC Presentation Peter J. Catto for the PSFC theory group MC & LH studies ITB investigations Neutrals & rotation BOUT improvements TORIC ICRF Mode Conversion

More information

Scaling of divertor heat flux profile widths in DIII-D

Scaling of divertor heat flux profile widths in DIII-D LLNL-PROC-432803 Scaling of divertor heat flux profile widths in DIII-D C. J. Lasnier, M. A Makowski, J. A. Boedo, S. L. Allen, N. H. Brooks, D. N. Hill, A. W. Leonard, J. G. Watkins, W. P. West May 20,

More information

Progress of Confinement Physics Study in Compact Helical System

Progress of Confinement Physics Study in Compact Helical System 1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress

More information

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU Edge and Internal Transport Barrier Formations in CHS S. Okamura, T. Minami, T. Akiyama, T. Oishi, A. Fujisawa, K. Ida, H. Iguchi, M. Isobe, S. Kado, K. Nagaoka, K. Nakamura, S. Nishimura, K. Matsuoka,

More information

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod Alcator C-Mod Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod B. LaBombard, R.L. Boivin, M. Greenwald, J. Hughes, B. Lipschultz, D. Mossessian, C.S.

More information

INTRODUCTION TO BURNING PLASMA PHYSICS

INTRODUCTION TO BURNING PLASMA PHYSICS INTRODUCTION TO BURNING PLASMA PHYSICS Gerald A. Navratil Columbia University American Physical Society - Division of Plasma Physics 2001 Annual Meeting, Long Beach, CA 1 November 2001 THANKS TO MANY PEOPLE

More information

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

GA A27418 THE ROLE OF ZONAL FLOWS AND PREDATOR- PREY OSCILLATIONS IN THE FORMATION OF CORE AND EDGE TRANSPORT BARRIERS GA A27418 THE ROLE OF ZONAL FLOWS AND PREDATOR- PREY OSCILLATIONS IN THE FORMATION OF CORE AND EDGE TRANSPORT BARRIERS by L. SCHMITZ, L. ZENG, T.L. RHODES, J.C. HILLESHEIM, W.A. PEEBLES, R.J. GROEBNER,

More information

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

Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod PFC/JA-96-42 Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod A.E. Hubbard, J.A. Goetz, I.H. Hutchinson, Y. In, J. Irby, B. LaBombard, P.J. O'Shea, J.A. Snipes, P.C. Stek, Y. Takase, S.M.

More information

Divertor Requirements and Performance in ITER

Divertor Requirements and Performance in ITER Divertor Requirements and Performance in ITER M. Sugihara ITER International Team 1 th International Toki Conference Dec. 11-14, 001 Contents Overview of requirement and prediction for divertor performance

More information

Light Impurity Transport Studies in Alcator C-Mod*

Light Impurity Transport Studies in Alcator C-Mod* Light Impurity Transport Studies in Alcator C-Mod* I. O. Bespamyatnov, 1 W. L. Rowan, 1 C. L. Fiore, 2 K. W. Gentle, 1 R. S. Granet, 2 and P. E. Phillips 1 1 Fusion Research Center, The University of Texas

More information

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

GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D by J.G. WATKINS, T.E. EVANS, I. JOSEPH, C.J. LASNIER, R.A. MOYER, D.L. RUDAKOV, O. SCHMITZ,

More information

Possible Experimental Tests of Pedestal Width/ Structure, Motivated by Theory/Modeling

Possible Experimental Tests of Pedestal Width/ Structure, Motivated by Theory/Modeling Possible Experimental Tests of Pedestal Width/ Structure, Motivated by Theory/Modeling R.J. Groebner PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Presented at DIII-D Pedestal

More information

Possible Pedestal Transport Theory Models And Modeling Tests

Possible Pedestal Transport Theory Models And Modeling Tests Possible Pedestal Transport Theory Models And Modeling Tests J.D. Callen, University of Wisconsin, Madison, WI 53706-1609 DIII-D Pedestal Transport Workshop, General Atomics, San Diego, CA, February 17,

More information

Controlling H-Mode Particle Transport with Modulated Electron Heating in DIII-D and Alcator C-Mod via TEM Turbulence

Controlling H-Mode Particle Transport with Modulated Electron Heating in DIII-D and Alcator C-Mod via TEM Turbulence Controlling H-Mode Particle Transport with Modulated Electron Heating in DIII-D and Alcator C-Mod via TEM Turbulence D.R. Ernst 1, K.H. Burrell 2, W. Guttenfelder 3, T.L. Rhodes 4, L. Schmitz 4, A.M. Dimits

More information

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX 1 Dependences of the ertor and plane heat flux widths in NSTX T.K. Gray1,2), R. Maingi 2), A.G. McLean 2), V.A. Soukhanovskii 3) and J-W. Ahn 2) 1) Oak Ridge Institute for Science and Education (ORISE),

More information

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak István Cziegler UCSD, Center for Energy Research Center for Momentum Transport and Flow Organization Columbia Seminar Feb

More information

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

Development and Validation of a Predictive Model for the Pedestal Height (EPED1) Development and Validation of a Predictive Model for the Pedestal Height (EPED1) P.B. Snyder 1 with R.J. Groebner 1, A.W. Leonard 1, T.H. Osborne 1, M. Beurskens 3, L.D. Horton 4, A.E. Hubbard 5, J.W.

More information

Optimization of Stationary High-Performance Scenarios

Optimization of Stationary High-Performance Scenarios Optimization of Stationary High-Performance Scenarios Presented by T.C. Luce National Fusion Program Midterm Review Office of Fusion Energy Science Washington, DC September, 6 QTYUIOP 8-6/TCL/rs Strategy

More information

Fast ion physics in the C-2U advanced, beam-driven FRC

Fast ion physics in the C-2U advanced, beam-driven FRC Fast ion physics in the C-2U advanced, beam-driven FRC Richard Magee for the TAE Team 216 US-Japan Workshop on the Compact Torus August 23, 216! High β FRC embedded in magnetic mirror is a unique fast

More information

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

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges by J.R. Ferron with T.C. Luce, P.A. Politzer, R. Jayakumar, * and M.R. Wade *Lawrence Livermore

More information

Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET

Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET JET P(98) F X Söldner et al Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET This document is intended for publication in the open literature. It is made available on

More information

Understanding physics issues of relevance to ITER

Understanding physics issues of relevance to ITER Understanding physics issues of relevance to ITER presented by P. Mantica IFP-CNR, Euratom/ENEA-CNR Association, Milano, Italy on behalf of contributors to the EFDA-JET Work Programme Brief summary of

More information

Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak

Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak by T.M. Wilks 1 with W.M. Stacey 1 and T.E. Evans 2 1 Georgia Institute of Technology 2 General Atomics Presented

More information

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

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL th IAEA Fusion Energy Conference Vilamoura, Portugal, to 6 November IAEA-CN-6/EX/P-7 STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL P.A. POLITZER, A.W. HYATT, T.C.

More information