PSI meeting, Aachen Germany, May 2012

Size: px
Start display at page:

Download "PSI meeting, Aachen Germany, May 2012"

Transcription

1 Constraining the divertor heat width in ITER D.G. Whyte 1, B. LaBombard 1, J.W. Hughes 1, B. Lipschultz 1, J. Terry 1, D. Brunner 1, P.C. Stangeby 2, D. Elder 2, A.W. Leonard 3, J. Watkins 4 1 MIT Plasma Science Fusion Center, Cambridge, MA, 02139, USA. 2 University of Toronto Institute for Aerospace Studies, Toronto, M3H 5T6, Canada. 3 General Atomics, San Diego, CA , USA. 4 Sandia National Laboratories, Albuquerque, NM 87185, USA. PSI meeting, Aachen Germany, May

2 Introduction The issue of the scrape-off layer (SOL) radial power width λ r, remains a critical and unresolved issue for designing magnetic fusion boundary plasmas First-principles explanations explaining λ r remain elusive Empirical attempts at estimating λ r, in large-scale devices like ITER have historically shown large amounts of scatter and poor self-consistency Recent activities have sought to improve λ r measurement fidelity in many present experiments (e.g. [LaBombard, Eich]). Regression analysis of these data [Makowski, Eich] and a heuristic drift model [Goldston] have suggested λ r ~ 1-3 mm for ITER, a factor of 5-10 lower than previous estimate raising serious concerns for ITER divertor viability. 2

3 Motivation It is desirable to develop methods of constraining λ r in ITER (and future fusion devices) independent of the λ r measurements themselves. We develop here such a method, constraining λ r based on SOL and pedestal pressure Sheath heat transmission Global power balance. This strategy is motivated by several recent observations and improvements in understanding these constraints 3

4 Sheath heat transmission coefficient γ~8-10 per standard sheath theory Accurate energy / plasma accounting in C-Mod divertor [Brunner] Gives confidence in using local plasma parameters at divertor to calculate heat flux since C-Mod most prototypical of ITER Vertical target High-Z metal target Density ~ m -3 High power density Grazing field of ~5 T. 4

5 H-mode pedestal stability modeling predictive of ITER pedestal Points here ITER p ped ~ 92 kpa or p 20 ~ 3000 p 20 2 n 20 T ev [Snyder] 5

6 Present experiments inform us to expected ratio of separatrix and pedestal pressure Must avoid persistent issue of unmeasured main ion temperature in vicinity of upstream separatrix. Example C-Mod upstream electron pressure profile Measure electron pressure at the divertor plate. Collisionality (high n, low T) assures T i ~T e Dynamic + static pressure must be conserved along separatrix for attached divertors (used here) p sep = 2 p div (Bohm criterion) T i ~ T e at top of pedestal from impurity ion T. Pressure of separatrix From divertor probes 6

7 Expect separatrix-to-pedestal pressure ratio ~5% for ITER From DIII-D and C-Mod divertor (separatrix) and upstream (pedestal)profiles JET point from upstream only [Beurskens] Best organizes to global power density ITER 7

8 Simple pressure + power balance model for ITER constrains λ r and T divertor Parallel exhaust area Divertor sheath heat flux Global divertor power exhaust. Q=10 P fusion = 500 MW P div = 50 MW 8

9 ITER divertor heat flux width must be λ r > 8 mm for divertor T < 100 ev T div =10 solution 9

10 Upstream separatrix temperature is also constrained by ITER operating near Greenwald density limit Multi-device database [Kallenbach] showed that in H-mode the separatrix density ~ core density Suggests most likely upstream density n 20 ~ f Gr ~ <

11 Upstream temperature provides further constraints on power exhaust Spitzer-Harm // conduction Flux-limiter // convection 11

12 Combining pressure + global power exhaust further defines allowed regions of Tdiv and λ r 12

13 Scanning allowed range of separatrix density λ r < 10 mm requires T div > 100 ev which has never been measured 13

14 Conclusions If the ITER divertor temperature ~ 10 ev (as presently expected) a power widths ~ 3 mm and less would require a separatrix pressure ~ pedestal pressure This clearly violates physical reasoning and/or the concept of a pedestal. For the divertor power width to be ~3 mm would require a divertor temperature ~ 1000 ev. This also likely violates physical reasoning regarding the thermal stability of open field lines and also strongly violates observation that all divertors to date have T < 60 ev (see discussion) This suggests we should consider simple pressure ratio constraints given here in understanding ITER (and reactor) heat flux widths. 14

15 References [LaBombard] B. LaBombard et al. Phys. Plasma (2011) [Snyder] P. Snyder, et al. Nucl. Fusion 51 (2011) [Eich] T. Eich, et al. PRL (2011) [Makowski] M. Makowski, APS-DPP 2011 [Brunner] D. Brunner, B. LaBombard Rev. Sci. Instrum (2012) [Goldston] R. Goldston Nucl. Fusion 52 (2012) [Beurskens] M. Beurskens Plasma Phys. Control. Fusion 51 (2009)

16 Physics Discussion: Divertor plasmas cannot be really hot because they are thermally unstable: // conduction case (width decreased to smallest allowed) P SOL 1 GW/m ev 999 ev P SOL 5 GW/m2 P rad P SOL P SOL 1000 ev 996 ev 995 ev 1 GW/m2 P rad 995 ev 5 GW/m2 P rad 996 ev ~200 ev. 990 ev < 50 ev 16

17 Physics Discussion: Divertor plasmas cannot be really hot because they are ionization unstable: // convection case (width decreased to smallest allowed) Γ SOL, P SOL 1 GW/m2, M=1, no source 1000 ev, n Gr Γ SOL, P SOL <1 GW/m2, M< ev, n Gr S ion 1000 ev, n Gr 1000 ev, n Gr P SOL 1 GW/m2 P rad 1000 ev, n Gr. <1000 ev, >n Gr 17

18 Physics Discussion: why the separatrix participation in the (known) pedestal stability is consistent with heat width trends Trend /w power Trend /w Ip 18

19 Physics Discussion: why the separatrix participation in the (known) pedestal stability is consistent with heat width trends Pedestal primarily regulated by peeling- ballooning instability NOT transport r/a ????? 19

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

GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK by M.A. MAKOWSKI, A.W. LEONARD, J.D. ELDER, C.J. LASNIER, J. NICHOLS, T.H. OSBORNE, P.C. STANGEBY and J.G. WATKINS OCTOBER 2012 DISCLAIMER

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

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

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

Critical edge gradients and flows with reversed magnetic field in Alcator C-Mod

Critical edge gradients and flows with reversed magnetic field in Alcator C-Mod Critical edge gradients and flows with reversed magnetic field in B. LaBombard, N. Smick, M. Greenwald, J.W. Hughes B. Lipschultz, K. Marr, J.L. Terry, Team Contributed talk JO1.00004 Presented at the

More information

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport 1 Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama Japan Atomic Energy Agency, Naka, Ibaraki-ken, 311-0193 Japan

More information

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D GA A24724 FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D by D.L. RUDAKOV, J.A. BOEDO, R.A. MOYER, N.H. BROOKS, R.P. DOERNER, T.E. EVANS, M.E. FENSTERMACHER, M. GROTH, E.M. HOLLMANN, S. KRASHENINNIKOV,

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

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

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod B. LaBombard, D. Brunner, A.Q. Kuang, W. McCarthy, J.L. Terry and the Alcator Team Presented at the International

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

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

Operational Phase Space of the Edge Plasma in Alcator C-Mod Operational Phase Space of the Edge Plasma in B. LaBombard, T. Biewer, M. Greenwald, J.W. Hughes B. Lipschultz, N. Smick, J.L. Terry, Team Contributed talk RO.00008 Presented at the 47th Annual Meeting

More information

Development of an experimental profile database for the scrape-off layer

Development of an experimental profile database for the scrape-off layer Development of an experimental profile database for the scrape-off layer M. Groth, 1 G.D. Porter, 1 W.M. Meyer, 1 A.W. Leonard, 2 T.H. Osborne, 2 D.P. Coster, 3 A. Kallenbach, 3 M. Wischmeier 3 N.H. Brooks,

More information

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

H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod J.W. Hughes, B. LaBombard, M. Greenwald, A. Hubbard, B. Lipschultz, K. Marr, R. McDermott, M. Reinke, J.L. Terry

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

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

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

ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS GA A2342 ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS by P.C. STANGEBY, J.G. WATKINS, G.D. PORTER, J.D. ELDER, S. LISGO, D. REITER, W.P. WEST, and D.G. WHYTE JULY 2 DISCLAIMER This report

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

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod EX/D- Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod B. LaBombard ), M. Greenwald ), R.L. Boivin ), B..A. Carreras 3), J.W. Hughes ), B. Lipschultz ), D. Mossessian ), C.S. Pitcher

More information

ICRF Loading Studies on Alcator C-Mod

ICRF Loading Studies on Alcator C-Mod ICRF Loading Studies on Alcator C-Mod 46 th Annual Meeting of the APS Division of Plasma Physics November 15-19, 19, 2004 A. Parisot, S.J. S.J. Wukitch,, P. Bonoli,, J.W. Hughes, B. Labombard,, Y. Lin,

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

Pedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability

Pedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability 1 EX/P4-15 Pedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability J.W. Hughes 1, P.B. Snyder 2, X. Xu 3, J.R. Walk 1, E.M. Davis 1, R.M.

More information

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices!

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices! Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,

More information

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

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer N. Smick, B. LaBombard MIT Plasma Science and Fusion Center PSI-19 San Diego, CA May 25, 2010 Boundary flows

More information

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod B. LaBombard, M. Umansky, R.L. Boivin, J.A. Goetz, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher, J.L.Terry,

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

GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING MEASUREMENTS IN DIII D

GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING MEASUREMENTS IN DIII D GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING by J.G. WATKINS, P.C. STANGEBY, J.A. BOEDO, T.N. CARLSTROM, C.J. LASNIER, R.A. MOYER, D.L. RUDAKOV, D.G. WHYTE JULY 2000 DISCLAIMER This report

More information

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer Alcator C-Mod Particle Transport in the Alcator C-Mod Scrape-off Layer B. LaBombard, R.L. Boivin, B. Carreras, M. Greenwald, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher, J.L. Terry, S.J. Zweben,

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

Evidence for Electromagnetic Fluid Drift Turbulence Controlling the Edge Plasma State in Alcator C-Mod

Evidence for Electromagnetic Fluid Drift Turbulence Controlling the Edge Plasma State in Alcator C-Mod Evidence for Electromagnetic Fluid Drift Turbulence Controlling the Edge Plasma State in B. LaBombard, J.W. Hughes, D. Mossessian, M. Greenwald, J.L. Terry, Team Contributed talk CO.00 Presented at the

More information

Advancing the predictive capability for pedestal structure through experiment and modeling

Advancing the predictive capability for pedestal structure through experiment and modeling Advancing the predictive capability for pedestal structure through experiment and modeling Highlights from the US Fusion Energy Science FY11 Joint Research Target J.W. Hughes 1, C.S. Chang 2, R.J. Groebner

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

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

Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod I. Cziegler J.L. Terry, B. LaBombard, J.W. Hughes MIT - Plasma Science and Fusion Center th 19 Plasma

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

Blob sizes and velocities in the Alcator C-Mod scrapeoff

Blob sizes and velocities in the Alcator C-Mod scrapeoff P1-59 Blob sizes and velocities in the Alcator C-Mod scrapeoff layer R. Kube a,b,*, O. E. Garcia a,b, B. LaBombard b, J. L. Terry b, S. J. Zweben c a Department of Physics and Technology, University of

More information

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

GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK by M. GROTH, G.D. PORTER, J.A. BOEDO, N.H. BROOKS, R.C. ISLER, W.P. WEST, B.D. BRAY, M.E. FENSTERMACHER, R.J. GROEBNER,

More information

Comparing Different Scalings of Parallel Heat Flux with Toroidal Magnetic Field [q with BT] M.L. Reinke. February, 2018

Comparing Different Scalings of Parallel Heat Flux with Toroidal Magnetic Field [q with BT] M.L. Reinke. February, 2018 PSFC/RR-18-4 Comparing Different Scalings of Parallel Heat Flux with Toroidal Magnetic Field [q with BT] M.L. Reinke February, 2018 Plasma Science and Fusion Center Massachusetts Institute of Technology

More information

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,

More information

Physics of the detached radiative divertor regime in DIII-D

Physics of the detached radiative divertor regime in DIII-D Plasma Phys. Control. Fusion 41 (1999) A345 A355. Printed in the UK PII: S741-3335(99)97299-8 Physics of the detached radiative divertor regime in DIII-D M E Fenstermacher, J Boedo, R C Isler, A W Leonard,

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

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas 1 Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas N. Hayashi 1), T. Takizuka 1), N. Aiba 1), N. Oyama 1), T. Ozeki 1), S. Wiesen 2), V. Parail 3) 1) Japan Atomic Energy Agency,

More information

Physics basis for similarity experiments on power exhaust between JET and ASDEX Upgrade with tungsten divertors

Physics basis for similarity experiments on power exhaust between JET and ASDEX Upgrade with tungsten divertors Physics basis for similarity experiments on power exhaust between JET and ASDEX Upgrade with tungsten divertors S. Wiesen, T. Eich, M. Bernert, S. Brezinsek, C. Giroud, E. Joffrin, A. Kallenbach, C. Lowry,

More information

Total Flow Vector in the C-Mod SOL

Total Flow Vector in the C-Mod SOL Total Flow Vector in the SOL N. Smick, B. LaBombard MIT Plasma Science and Fusion Center APS-DPP Annual Meeting Atlanta, GA November 3, 2009 Motivation and Goals Measurements have revealed high parallel

More information

Cross-Field Transport in the SOL: Its Relationship to Main Chamber and Divertor Neutral Control in Alcator C-Mod

Cross-Field Transport in the SOL: Its Relationship to Main Chamber and Divertor Neutral Control in Alcator C-Mod Cross-Field Transport in the SOL: Its Relationship to Main Chamber and Divertor Neutral Control in Alcator C-Mod B. LaBombard, B. Lipschultz, J.A. Goetz, C.S. Pitcher, N. Asakura 1), R.L. Boivin, J.W.

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

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET Journal of Nuclear Materials 363 365 (2007) 989 993 www.elsevier.com/locate/jnucmat Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET T. Eich a, *, A.

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

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST CCFE-PR(13)33 J. R. Harrison, G. M. Fishpool and A. Kirk L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST Enquiries about copyright and reproduction should in the first instance

More information

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes S. Gangadhara,. Laombard M.I.T. Plasma Science and Fusion Center, 175 Albany St., Cambridge, MA 2139 USA Abstract Accurate

More information

Particle and Energy Transport in the SOL of DIII-D and NSTX

Particle and Energy Transport in the SOL of DIII-D and NSTX 1 EX/P4-2 Particle and Energy Transport in the SOL of DIII-D and NSTX J.A. Boedo 1), R.J. Maqueda 2), D.L. Rudakov 1), G.R. McKee 3), H. Kugel 4), R. Maingi 5), N. Crocker 6), R.A. Moyer 1), V.A. Soukhanovskii

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

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

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

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

TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings

TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings T. Onjun 1), A.H. Kritz ), G. Bateman ), A. Pankin ) 1) Sirindhorn International Institute of Technology, Klong Luang, Pathumthani,

More information

I-mode and H-mode plasmas at high magnetic field and pressure on Alcator C-Mod

I-mode and H-mode plasmas at high magnetic field and pressure on Alcator C-Mod I-mode and H-mode plasmas at high magnetic field and pressure on Alcator C-Mod A. E. Hubbard, J. W Hughes, S.-G. Baek, D. Brunner, I. Cziegler 1, E. Edlund, T. Golfinopoulos, M.J. Greenwald, J. Irby, B.

More information

Modelling radiative power exhaust in view of DEMO relevant scenarios

Modelling radiative power exhaust in view of DEMO relevant scenarios Modelling radiative power exhaust in view of DEMO relevant scenarios 2 nd IAEA Technical Meeting November 14th 2017 S. Wiesen, M. Wischmeier, M. Bernert, M. Groth, A. Kallenbach, R. Wenninger, S. Brezinsek,

More information

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer PHYSICS OF PLASMAS VOLUME 7, NUMBER 11 NOVEMBER 2000 Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer R. Nachtrieb a) Lutron Electronics Co.,

More information

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant Implementation of a long leg X-point target divertor in the ARC fusion pilot plant A.Q. Kuang, N.M. Cao, A.J. Creely, C.A. Dennett, J. Hecla, H. Hoffman, M. Major, J. Ruiz Ruiz, R.A. Tinguely, E.A. Tolman

More information

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Modelling of JT-60U Detached Divertor Plasma using SONIC code J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Modelling of JT-60U Detached Divertor Plasma using SONIC code Kazuo HOSHINO, Katsuhiro SHIMIZU, Tomonori TAKIZUKA, Nobuyuki ASAKURA and Tomohide NAKANO Japan

More information

IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT IN DIII-D

IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT IN DIII-D 20 th IAEA Fusion Energy Conference Vilamoura, Portugal, 1 to 6 November 2004 IAEA-CN-116/EX/P5-19 IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT

More information

Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod

Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod I.C. Faust, G.M. Wallace, S.G. Baek, D. Brunner, B. LaBombard, R.R. Parker, Y. Lin, S. Shiraiwa, J.L. Terry,

More information

The Future of Boundary Plasma and Material Science

The Future of Boundary Plasma and Material Science The Future of Boundary Plasma and Material Science Dennis Whyte Plasma Science & Fusion Center, MIT, Cambridge USA Director, Plasma Surface Interaction Science Center (psisc.org) APS Sherwood Meeting of

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

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

Edge Plasma Energy and Particle Fluxes in Divertor Tokamaks

Edge Plasma Energy and Particle Fluxes in Divertor Tokamaks Edge Plasma Energy and Particle Fluxes in Divertor Tokamaks Alberto Loarte European Fusion Development Agreement Close Support Unit - Garching Alberto Loarte New Trends in Plasma Physics II Max-Planck-Institut

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

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas DIVIMP simulation of W transport in the SOL of JET H-mode plasmas A. Järvinen a, C. Giroud b, M. Groth a, K. Krieger c, D. Moulton d, S. Wiesen e, S. Brezinsek e and JET- EFDA contributors¹ JET-EFDA, Culham

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

OV/2-5: Overview of Alcator C-Mod Results

OV/2-5: Overview of Alcator C-Mod Results OV/2-5: Overview of Alcator C-Mod Results Research in Support of ITER and Steps Beyond* E.S. Marmar on behalf of the C-Mod Team 25 th IAEA Fusion Energy Conference, Saint Petersburg, Russia, 13 October,

More information

Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER

Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER C.S. Chang 1, S. Ku 1, A. Loarte 2, V. Parail 3, F. Köchl 4, M. Romanelli 3, R. Maingi 1, J.-W. Ahn 5, T. Gray 5, J.

More information

ITER. Power and Particle Exhaust in ITER ITER

ITER. Power and Particle Exhaust in ITER ITER Power and Particle Exhaust in ITER ITER G. Janeschitz, C. Ibbott, Y. Igitkhanov, A. Kukushkin, H. Pacher, G. Pacher, R. Tivey, M. Sugihara, JCT and HTs San Diego.5.2 Power and Particle Exhaust in ITER

More information

Dimensionless pedestal identity plasmas on Alcator C-Mod C

Dimensionless pedestal identity plasmas on Alcator C-Mod C Dimensionless pedestal identity plasmas on Alcator C-Mod C and JET G P Maddison 1, A E Hubbard 2, J W Hughes 2, I M Nunes 3, M N A Beurskens 1, S K Erents 1, Pasqualotto 4, E Giovannozzi 5, A Alfier 4,

More information

EFDA European Fusion Development Agreement - Close Support Unit - Garching

EFDA European Fusion Development Agreement - Close Support Unit - Garching Multi-machine Modelling of Divertor Geometry Effects Alberto Loarte EFDA CSU -Garching Acknowledgements: K. Borrass, D. Coster, J. Gafert, C. Maggi, R. Monk, L. Horton, R.Schneider (IPP), A.Kukushkin (ITER),

More information

Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas

Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas P. T. Bonoli*, S. G. Baek, B. LaBombard, K. Filar, M. Greenwald, R. Leccacorvi,

More information

Multi-machine comparisons of divertor heat flux mitigation by radiative cooling with nitrogen

Multi-machine comparisons of divertor heat flux mitigation by radiative cooling with nitrogen 1 ITR/P1-28 Multi-machine comparisons of divertor heat flux mitigation by radiative cooling with nitrogen A. Kallenbach 1, M. Bernert 1, R. Dux 1, T. Eich 1, C. Giroud 2, A. Herrmann 1, J.W. Hughes 3,

More information

H-mode Pedestal Enhancement and Improved Confinement in DIII-D with Lithium Injection

H-mode Pedestal Enhancement and Improved Confinement in DIII-D with Lithium Injection H-mode Pedestal Enhancement and Improved Confinement in DIII-D with Lithium Injection by G.L. Jackson, with R. Maingi, T.H. Osborne, D.K. Mansfield, C.P. Chrobak, B.A. Grierson, A.G. McLean, Z. Yan, S.L.

More information

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment. Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment E. Kolemen a, S.L. Allen b, B.D. Bray c, M.E. Fenstermacher b, D.A. Humphreys c, A.W. Hyatt c, C.J. Lasnier b,

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

GA A26891 A FIRST PRINCIPLES PREDICTIVE MODEL OF THE PEDESTAL HEIGHT AND WIDTH: DEVELOPMENT, TESTING, AND ITER OPTIMIZATION WITH THE EPED MODEL GA A26891 A FIRST PRINCIPLES PREDICTIVE MODEL OF THE PEDESTAL HEIGHT AND WIDTH: DEVELOPMENT, TESTING, AND ITER OPTIMIZATION WITH THE EPED MODEL by P.B. SNYDER, R.J. GROEBNER, J.W. HUGHES, T.H. OSBORNE,

More information

Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options

Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options A.M. Garofalo, T. Petrie, J. Smith, V. Chan, R. Stambaugh (General Atomics) J. Canik, A. Sontag, M. Cole (Oak Ridge National Laboratory)

More information

Partial detachment of high power discharges in ASDEX Upgrade

Partial detachment of high power discharges in ASDEX Upgrade Partial detachment of high power discharges in ASDEX Upgrade A. Kallenbach 1, M. Bernert 1, M. Beurskens, L. Casali 1, M. Dunne 1, T. Eich 1, L. Giannone 1, A. Herrmann 1, M. Maraschek 1, S. Potzel 1,

More information

Experimental results and modelling of ASDEX Upgrade partial detachment

Experimental results and modelling of ASDEX Upgrade partial detachment Experimental results and modelling of ASDEX Upgrade partial detachment M. Wischmeier 1 With thanks to X. Bonnin 2, P. Börner 3, A. Chankin 1, D. P. Coster 1, M. Groth 4, A. Kallenbach 1, V. Kotov 3, H.

More information

GA A22636 RECENT H MODE DENSITY LIMIT EXPERIMENTS ON DIII D

GA A22636 RECENT H MODE DENSITY LIMIT EXPERIMENTS ON DIII D GA A22636 RECENT H MODE DENSITY LIMIT EXPERIMENTS ON DIII D by M.A. MAHDAVI, R. MAINGI, R.J. LA HAYE, T.C. JERNIGAN, T.W. PETRIE, L.R. BAYLOR, A.W. HYATT, A.W. LEONARD, M. MURAKAMI, L.W. OWENS, R.T. SNIDER,

More information

Evidence for electromagnetic fluid drift turbulence controlling the edge plasma state in the Alcator C-Mod tokamak

Evidence for electromagnetic fluid drift turbulence controlling the edge plasma state in the Alcator C-Mod tokamak PSFC/JA-05-4 Evidence for electromagnetic fluid drift turbulence controlling the edge plasma state in the Alcator C-Mod tokamak B. LaBombard, J.W. Hughes, D. Mossessian, M. Greenwald, B. Lipschultz, J.L.

More information

Attainment of a stable, fully detached plasma state in innovative divertor configurations

Attainment of a stable, fully detached plasma state in innovative divertor configurations Attainment of a stable, fully detached plasma state in innovative divertor configurations M.V. Umansky, Lawrence, Livermore National Laboratory, Livermore, CA 94550, USA O. Izacard, M.E. Rensink, T.D.

More information

Potentials, E B drifts, and uctuations in the DIII-D boundary

Potentials, E B drifts, and uctuations in the DIII-D boundary Journal of Nuclear Materials 266±269 (1999) 1145±1150 Potentials, E B drifts, and uctuations in the DIII-D boundary R.A. Moyer a, *, R. Lehmer a, J.A. Boedo a, J.G. Watkins b,x.xu c, J.R. Myra d, R. Cohen

More information

Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants

Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants C. E. Kessel 1, M. S. Tillack 2, and J. P. Blanchard 3 1 Princeton Plasma Physics Laboratory 2 University of California, San Diego

More information

3D analysis of impurity transport and radiation for ITER limiter start-up configurations

3D analysis of impurity transport and radiation for ITER limiter start-up configurations 3D analysis of impurity transport and radiation for ITER limiter start-up configurations P2-74 X. Zha a*, F. Sardei a, Y. Feng a, M. Kobayashi b, A. Loarte c, G. Federici c a Max-Planck-Institut für Plasmaphysik,

More information

THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST

THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST GA A25482 13 C-TRACER EXPERIMENTS IN DIII-D PRELIMINARY IN THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST by P.C. STANGEBY, S.L. ALLEN, N. BEKRIS, N.H. BROOKS,

More information

Correlations of ELM frequency with pedestal plasma characteristics

Correlations of ELM frequency with pedestal plasma characteristics cpp header will be provided by the publisher Correlations of ELM frequency with pedestal plasma characteristics G. Kamberov 1 and L. Popova 2 1 Stevens Institute of Technology, Hoboken NJ, USA 2 Institute

More information

IF2011 Pedestal/JRT Summary. J.W. Hughes 21 Jan 2011

IF2011 Pedestal/JRT Summary. J.W. Hughes 21 Jan 2011 IF2011 Pedestal/JRT Summary J.W. Hughes 21 Jan 2011 Predictive capability for the H-mode pedestal is the subject of the FY11 JRT Statement of FY11 FES Joint Research Target: (1) Improve the understanding

More information

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U 1 EX/P4-25 Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-6U T. Nakano, H. Kubo, N. Asakura, K. Shimizu and S. Higashijima Japan Atomic Energy Agency, Naka,

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

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

Helium ELMy H-modes in Alcator C-Mod in Support of ITER Helium Operating Phases Helium ELMy H-modes in Alcator C-Mod in Support of ITER Helium Operating Phases C. E. Kessel 1, S. M. Wolfe 2, M. L. Reinke 3, M. A. Chilenski 2, J. W. Hughes 2, Y. Lin 2, S. Wukitch 2 and the C-Mod Team

More information

UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance

UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance N.S. Wolf, G.D. Porter, M.E. Rensink, T.D. Rognlien Lawrence Livermore National Lab, And the DIII-D team

More information

Simulation of Plasma Flow in the DIII-D Tokamak

Simulation of Plasma Flow in the DIII-D Tokamak UCRL-JC-129497 Preprint Simulation of Plasma Flow in the DIII-D Tokamak G.D Porter, T D. Rognlien, N. Wolf, J Boedo, R.C Isler This paper was prepared for submittal to 1998 International Congress on Plasma

More information

Linjin Zheng, Infernal Modes at Tokamak H- mode Pedestal A Physics Interpreta;on for Edge Harmonic Oscilla;on (EHO)

Linjin Zheng, Infernal Modes at Tokamak H- mode Pedestal A Physics Interpreta;on for Edge Harmonic Oscilla;on (EHO) International Sherwood Fusion Theory Conference, Austin, May 2-4, 2011 Infernal Modes at Tokamak H- mode Pedestal A Physics Interpreta;on for Edge Harmonic Oscilla;on (EHO) Linjin Zheng, M. T. Kotschenreuther,

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

Fusion Development Facility (FDF) Divertor Plans and Research Options

Fusion Development Facility (FDF) Divertor Plans and Research Options Fusion Development Facility (FDF) Divertor Plans and Research Options A.M. Garofalo, T. Petrie, J. Smith, M. Wade, V. Chan, R. Stambaugh (General Atomics) J. Canik (Oak Ridge National Laboratory) P. Stangeby

More information