Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod
|
|
- Rafe Logan
- 5 years ago
- Views:
Transcription
1 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. Pitcher, J.L. Terry, S.J. Zweben, Alcator C-Mod Group Invited talk BI.6 Presented at the 42nd Annual Meeting of the APS Division of Plasma Physics combined with the th International Congress on Plasma Physics October 23-27, 2 Qu bec City, Canada
2 Motivation: Cross-field particle transport (Γ ) in SOL and its dependence on discharge conditions impacts tokamak operation & design Γ determines level of plasma/wall interaction in main-chamber neutral pressures (=> confinement) impurity sources => impacts divertor design Low Transport High Transport SOL Core Plasma Core Plasma ions neutrals Divertor C-Mod Q: What will be operating regime in a reactor? Heat convection across separatrix and its scaling may play role in tokamak density limit Goals: Characterize and understand Γ : - empirical scalings - underlying turbulence - relationship to tokamak density limit
3 Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Horizontal Scanning Probe Midplane Dα Fluctuations Behavior Near Discharge Density Limit Vertical Scanning Probe Divertor Probes
4 Scrape-off Layer Density Profiles Exhibit a "Two-Exponential" Decay 2 SOL Density Profiles n e /n G =.43 [Ohmic L-Mode] Limiter Shadow (m-3) 9 8 Near SOL n e /n G = Separatrix Far SOL Distance into SOL (mm) Near SOL: steep decay, λ n ~ 2 to 8 mm Far SOL: shallow decay, λ n ~ 8 to > mm At low ne, density at limiter edge is less than ~/ of separatrix density Density at limiter edge increases sharply with increasing ne => Always some level of main-chamber (limiter) recycling
5 Main Chamber Ionization and Fluxes in the Far SOL Are Large Compared to Flows Towards Div./Baffle 23 Main Chamber Ionization (Dα) Ion Flux (D + /s) 22 Flux on Divertor (Div. Probes) Flow Towards Divertor/Baffle (Mach Probe) ne/n G Recycling in Main Chamber SOL is primarily balance by fluxes onto main-chamber walls Poloidal flows to divertor/baffle are weak Main-Chamber Recycling Regime (MCR) persists over wide parameter range M.V. Umansky, et al. Phys. Plasmas 5, 3373 (998).
6 A New View of Particle Transport Processes in SOL Old Paradigm: SOL density decays "exponentially" because... plasma drains along field lines towards divertor/baffle SOL Profiles Density Limiter Shadow Ionization FluxTowards Divertor/Baffle Dominates Separatrix SOL drained by parallel flow New Paradigm: SOL density decays "exponentially" because... cross-field transport velocity increases across SOL, maintaining cross-field flux towards wall SOL Profiles Density Limiter Shadow Flux Towards Limiter/Wall Dominates Velocity Ionization Separatrix
7 Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Fluctuations Edge Thomson Scattering Tangential- Viewing Ly α Array Horizontal Scanning Probe Behavior Near Discharge Density Limit
8 (m (m -3 s - ) (m -2 s - ) -3 )2 (m 2 s - ) In MCR Regime, Cross-Field Diffusion Coefficient Profiles (Deff) can be Inferred Directly from Profile Measurements n Sion Γ Deff Separatrix Distance into SOL (mm) Limiter Shadow - Density n e /n G Ionization Source (from Lyα profiles) - Cross-Field Flux Profile - Effective Diffusion Coefficient: Deff = -Γ / n Persistent trend of Deff increasing by ~ or more with distance from separatrix => variation in Deff reflects variation in n Deff increases with discharge density => Γ gets larger, n gets smaller Method benchmarked against UEDGE modeling Deff (χ eff ) increasing seen before: ASDEX, JT-6, JET,...
9 Magnitude of Deff in Near SOL is Correlated with Collisionality in Near SOL. Regression Analysis of D eff, 2 mm into SOL Te -3.8 n. Ip -.3 BT.8 64 Ohmic L-Mode Datapoints:.8 < ne < 2.5x 2 m -3.6 < Ip <. MA 4 < B T < 6 tesla.4 < ne/n G <.47 (m2 s-)... (λei/l) -.7 Multiple Correlation Coefficient =.8 4 Parameter Regression: => Suggests (B T /Ip), q, or L dependence (m2 s-). Multiple Correlation Coefficient = (m2 s-) Parameter Regression: => Statistics point to (λei/l) as most relevant parameter => Deff correlates with local collisionality: Deff ~ (λei /L) -.7 Trend: ne/n G => λei/l => Deff near sep.
10 Cross-Field Heat Convection to Limiter/Wall Competes with Parallel Conduction Losses to Divertor at Moderate ne/n G Finite Te on open field lines => power conducted to divertor: Qdiv T 7/2 /L δρ' ρ Cross-field particle fluxes (Γ ) => power convected: Qconv ~ 5 Te Γ A sep 5 Electron Temperature (ev). Power Through Flux Surface ρ (MW)... ne/n G =.9 Qdiv ne/n G =.9 ne/n G =.43 ne/n G =.43 Qconv Qconv Qdiv ρ (mm) Limiter Distance into SOL Shadow Qconv > Qdiv only in far sol Qconv > Qdiv over entire SOL At low density, heat losses in Near SOL are dominated by parallel conduction to Divertor At moderate density, cross-field heat convection to Limiter/Wall exceeds conduction losses to Divertor/Baffle over entire SOL
11 A New View of Heat Transport Processes in SOL Old Paradigm: (in absence of a "radiating mantle") Parallel e - conduction to divertor dominates heat losses in Near SOL region Te at separatrix (Tsep) is a weak function of λ T e and SOL power (P sol): Psol Tsep (Psol / λ T e )2/7 Modified Paradigm: Parallel e - conduction and cross-field heat convection contribute to heat losses in Near SOL region (charge exchange also can contribute) Psol At low collisionality, parallel conduction regulates Tsep: Tsep (Psol / λ T e )2/7 At high collisionality, heat convection becomes large, Tsep is reduced and is no longer "regulated" by this law!
12 Outline of Talk Main-Chamber Recycling Diagnostics: Effective Cross- Field Particle Diffusitives (Deff) & Scalings Cross-Field Heat Convection Limiter-Shadow Particle Flux Probe Horizontal Scanning Probe Fluctuations Turbulence Imaging Behavior Near Discharge Density Limit
13 ..5 Time (milliseconds) Time (milliseconds) Time (milliseconds) Time (milliseconds) Fluctuations Exhibit Different Character in Near and Far SOL Regions ( 2 m -3 ). Near SOL SOL Density Profile Far SOL Distance into SOL (mm) Isat/<Isat> "Snapshots" τ ac ~.2µs 2.2µs 5.5µs 3µs µs Time (ms) Limiter Shadow 25 Auto-Correlation Functions Isat/<Isat> (µs) Near SOL (steep n profile): -> moderate amplitude, "random" fluctuations Far SOL (flatter n profile): -> large amplitude, intermittent Isat "bursts" => Consistent with Deff with distance into SOL
14 2-D Turbulence Imaging: Intermittent, ~ cm Scale "Blobs" of Emission Extend into Far SOL Near SOL Separatrix Density Far SOL Limiter Shadow Turbulence Imaging: 2-D Images of Da emission, looking along field lines at a "plume" from D2 gas nozzle ~ mm spatial resolution 2 µs exposure times 7 ms between exposures 2 cm ~ cm scale blobs intermittently occupy Far SOL zone, and extend to Limiter Shadow Intermittent "Blobs" (2-D imaging) and "Bursts" (probes) are consistent with large density and temperature (?) perturbations rapidly transporting particles and energy to Limiter/Walls More on 2-D edge turbulence Imaging: S.J. Zweben - oral JO.5 Tuesday PM J.L. Terry - poster UP.6 Thursday AM
15 ..2.4 seconds seconds.6.8. (MA) Collisionality at the Separatrix and Heat Convection to Limiter/Wall Increases as Discharge Density Limit is Approached (MW) Diverted Discharge with Ramping ne/n G. 5 Plasma Current Input Power ne/n G Line Averaged Density Radiated Power λei/l (seconds) Horizontal Scanning Probe records profiles at three times ( 2 m -3 ).8.4 Heat Convection to Limiter/Wall based on Limiter Particle Flux Probe λei/l, mm into SOL As density limit is approached: λei/l near separatrix drops dramatically Radiation and Convection to Limiter/Wall are comparable and mostly account for input power Near density limit: Radiation + Convection to Walls ~ Input Power
16 Near Density Limit: Large Amplitude, Long- Correlation Time Fluctuations Envelop Entire SOL and Cross Separatrix n / n G at separatrix does not increase!.4. SOL Profiles Density / n G ne/n G (ev) Electron Temperature (µs) -2 Auto-Correlation Times (Vf data) Separatrix Distance into SOL (mm) RMS Isat/<Isat> Near density limit: SOL n & Te profiles become flat, Tsep low ~ 25 ev! Fluctuations characteristic of "Far SOL" now occur everywhere, even across the separatrix => Consistent with large Convection Losses
17 Summary C-Mod SOL Core Plasma Divertor SOL density profiles exhibit a "twoexponential" decay: Near and Far SOL Yet, Main-chamber plasma exhausts primarily onto Limiter/Wall surfaces! - Why? - => New Particle Transport Paradigm: Density "decays exponentially" because... cross-field transport (Deff ) increases rapidly with distance into SOL... not because parallel flows "drain" SOL plasma Particle (Deff) and heat convection near separatrix increases with collisionality: Deff ~ (λei /L) -.7 => Heat Transport Paradigm Modified: At moderate collisionality (ne/n G ~.5), crossfield heat convection exceeds conduction losses Tsep no longer regulated by "conduction law": Tsep (Psol / λ T e )2/7
18 Summary (page 2) Fluctuation behavior supports picture of particle & energy transport increasing with distance into SOL Near SOL: (steep density profile) low amplitude "random" fluctuations Far SOL: (flat density profile) large amplitude intermittent "bursts" in Isat and ~ cm "blobs" in Dα, extending into Limiter Shadow => New Insight on Density Limit Physics: As density limit is approached, λei/l near separatrix drops and transport across the SOL increases dramatically Heat Convection to Limiter/Wall becomes large fraction of input power "Bursty" fluctuations (large transport) occur over entire SOL and begins to attack plasma on closed flux surfaces ~ at limit: Radiation + Convection to Wall ~ Input Power Rapid increase of Heat Convection as edge plasma cools may play role in thermal instability leading to disruption
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 informationCross-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 informationDensity 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 informationCross-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 informationOperational 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 informationEvidence 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 informationCritical 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 informationCross-field plasma transport and main chamber recycling in diverted plasmas on Alcator C-Mod. Abstract
Cross-field plasma transport and main chamber recycling in diverted plasmas on Alcator C-Mod B. LaBombard *, M.V. Umansky, R.L. Boivin, J.A. Goetz, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher,
More informationEffect 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 informationPSI meeting, Aachen Germany, May 2012
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
More informationPedestals 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 informationEvidence 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 informationH-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 informationConnections 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 informationFAR 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 informationArbiTER studies of filamentary structures in the SOL of spherical tokamaks
ArbiTER studies of filamentary structures in the SOL of spherical tokamaks D. A. Baver, J. R. Myra, Research Corporation F. Scotti, Lawrence Livermore National Laboratory S. J. Zweben, Princeton Plasma
More informationRapid changes of turbulence propagation direction in the edge of
Rapid changes of turbulence propagation direction in the edge of I. Cziegler, J. L. Terry MIT Plasma Science and Fusion Center APS Division of Plasma Physics Dallas TX, November 8 Motivations for edge/sol
More informationBlob 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 informationHelium-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 informationScaling 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 informationFlow 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 informationDriving 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 informationPower 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 informationDrift-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 informationPlasma Science and Fusion Center
Plasma Science and Fusion Center Turbulence and transport studies in ALCATOR C Mod using Phase Contrast Imaging (PCI) Diagnos@cs and Comparison with TRANSP and Nonlinear Global GYRO Miklos Porkolab (in
More informationComments on Particle and Energy Balance in the Edge Plasma of Alcator C-Mod
PSFC/JA-98-12 Comments on Particle and Energy Balance in the Edge Plasma of Alcator C-Mod M.V. Umansky, S.I. Krasheninnikov, B. LaBombard, J.L. Terry April 1998 Plasma Science and Fusion Center Massachusetts
More informationStatistical Analysis of Fluctuation Characteristics at High- and Low-Field Sides in L-mode SOL Plasmas of JT-60U
1 EX/P4-18 Statistical Analysis of Fluctuation Characteristics at High- and Low-Field Sides in L-mode SOL Plasmas of JT-60U N. Ohno1), H. Tanaka1), N. Asakura2), Y. Tsuji1), S. Takamura3), Y. Uesugi4)
More informationOVERVIEW 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 informationEnhanced 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 informationFluctuation statistics in the scrape-off layer of Alcator C-Mod
Fluctuation statistics in the scrape-off layer of Alcator C-Mod R. Kube, O. E. Garcia, B. LaBombard, and J. L. Terry We study long time series of the ion saturation current and floating potential, obtained
More informationInvestigation of causes for the discrepancy between the measured and modeled helium emissions using a gas puff imaging diagnostic
Investigation of causes for the discrepancy between the measured and modeled helium emissions using a gas puff imaging diagnostic S. Baek, J. Terry, D. P. Stotler*, D. Brunner, B. LaBombard MIT Plasma
More informationObservation 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 informationGA 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 informationReview of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance
Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance Alberto Loarte European Fusion Development Agreement Close Support Unit - Garching
More information1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5.
1. Motivation power exhaust in JT-60SA tokamak 2. Tool COREDIV code 3. Operational scenarios of JT-60SA 4. Results 5. Conclusions K. Gałązka Efficient power exhaust in JT-60SA by COREDIV Page 2 The Institute
More informationPhysics 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 informationProgress 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 informationParticle 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 informationTHE 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 informationLocal 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 informationPower Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod
PFC/JA-94-15 Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod J.A. Goetz, B. Lipschultz, M.A. Graf, C. Kurz, R. Nachtrieb, J.A. Snipes, J.L. Terry Plasma
More informationEFFECT 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 informationABSTRACT, POSTER LP1 12 THURSDAY 11/7/2001, APS DPP CONFERENCE, LONG BEACH. Recent Results from the Quiescent Double Barrier Regime on DIII-D
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.
More informationEdge 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 informationDivertor 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 informationCharacteristics 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 informationA kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva
A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva CRPP - EPFL SPS Annual Meeting 2014 02.07.2014 CRPP The tokamak
More informationEdge Zonal Flows and Blob Propagation in Alcator C-Mod P5.073 EPS 2011
Edge Zonal Flows and Blob Propagation in Alcator C-Mod S.J. Zweben 1, J.L. Terry 2, M. Agostini 3, B. Davis 1, O. Grulke 4,J. Hughes 2, B. LaBombard 2 D.A. D'Ippolito 6, R. Hager 5, J.R. Myra 6, D.A. Russell
More informationReduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection
Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection M. Porkolab, P. C. Ennever, S. G. Baek, E. M. Edlund, J. Hughes, J. E.
More informationExperimental investigation of the parallel structure of fluctuations in the scrape-off layer of Alcator C-Mod
Experimental investigation of the parallel structure of fluctuations in the scrape-off layer of Alcator C-Mod O. Grulke Max Planck Institute for Plasma Physics, Greifswald Branch, EURATOM Association,
More informationA novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments
A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments B. LaBombard, S. Gangadhara, B. Lipschultz, S. Lisgo a, D.A. Pappas, C.S. Pitcher, P. Stangeby a, J.
More informationStudy 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 informationICRF 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 informationExhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France
Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.
More informationEFDA 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 informationTokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011
Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor
More informationProgress in the ITER Physics Basis
Progress in the ITER Physics Basis Chapter 4. Power and Particle Control ITPA Scrape-off Layer and Divertor Physics Topical Group A. Loarte (EFDA-CSU Garching), B. Lipschultz (MIT-PSFC), A.S. Kukushkin
More informationEvaluation of Anomalous Fast-Ion Losses in Alcator C-Mod
Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod S. D. Scott Princeton Plasma Physics Laboratory In collaboration with R. Granetz, D. Beals, M. Greenwald MIT PLASMA Science and Fusion Center W.
More informationSome Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact
Some Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact Peter Stangeby 4 September 2003 1. Fig. 1 shows an example of a suitable magnetic configuration for application
More informationErosion and Confinement of Tungsten in ASDEX Upgrade
ASDEX Upgrade Max-Planck-Institut für Plasmaphysik Erosion and Confinement of Tungsten in ASDEX Upgrade R. Dux, T.Pütterich, A. Janzer, and ASDEX Upgrade Team 3rd IAEA-FEC-Conference, 4.., Daejeon, Rep.
More informationPredicting 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 informationGA 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 informationSimulation 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 information3D 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 informationarxiv: v1 [physics.plasm-ph] 14 Jul 2014
An experimental investigation on the high density transition of the Scrape-off Layer transport in ASDEX Upgrade arxiv:147.3618v1 [physics.plasm-ph] 14 Jul 214 D. Carralero 1, G. Birkenmeier 1, H.W. Müller
More informationGyrokine.c Analysis of the Linear Ohmic Confinement Regime in Alcator C- Mod *
Gyrokine.c Analysis of the Linear Ohmic Confinement Regime in Alcator C- Mod * Miklos Porkolab in collabora.on with J. Dorris, P. Ennever, D. Ernst, C. Fiore, M. Greenwald, A. Hubbard, E. Marmar, Y. Ma,
More informationDevelopment of a New Gas Puff Imaging Diagnostic on the HL-2A Tokamak
Development of a New Gas Puff Imaging Diagnostic on the HL-2A Tokamak B.Yuan a,b, M.Xu b,*, Y.Yu a,*, L.Zang b, R.Hong c, C.Chen b, Z.Wang b,l.nie b, R.Ke b, D.Guo b, Y.Wu a,b, T.Long b, S.Gong a,b, H.Liu
More informationTurbulence and flow in the Large Plasma Device
Turbulence and flow in the Large Plasma Device D.A. Schaffner, T.A. Carter, P. Popovich, B. Friedman Dept of Physics, UCLA Gyrokinetics in Laboratory and Astrophysical Plasmas Isaac Newton Institute of
More informationFlow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe
Flow Measurements in the DIII-D Divertor Flow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe J. Boedo, R. Lehmer, R. Moyer, J. Watkins, D. Hill, T.
More informationPlasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak
1 EX/P3-21 Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak L.H Yao 1), B.B. Feng 1), C.Y. Chen 1), Z.B. Shi 1), B.S. Yuan 1), W,W. Xiao 1), Y. Zhou
More informationRadial impurity transport in the H mode transport barrier region in Alcator C-Mod
Radial impurity transport in the H mode transport barrier region in Alcator C-Mod T. Sunn Pedersen, R.S. Granetz, A.E. Hubbard, I.H. Hutchinson, E.S. Marmar, J.E. Rice, J. Terry Plasma Science and Fusion
More informationElectron temperature barriers in the RFX-mod experiment
Electron temperature barriers in the RFX-mod experiment A. Scaggion Consorzio RFX, Padova, Italy Tuesday 5 th October 2010 ADVANCED PHYSICS LESSONS 27/09/2010 07/10/2010 IPP GARCHING JOINT EUROPEAN RESEARCH
More informationDivertor 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 informationModeling neutral-plasma interactions in scrape-off layer (SOLT) simulations*
Modeling neutral-plasma interactions in scrape-off layer (SOLT) simulations* D. A. Russell and J. R. Myra Research Corporation Boulder CO USA Presented at the US Transport Task Force Workshop Williamsburg
More informationVolume Recombination and Detachment in JET Divertor Plasmas
JET CP(98)1 Volume Recombination and Detachment in JET Divertor Plasmas G M McCracken, R D Monk, A Meigs, L Horton, L C Ingesson, J Lingertat, G F Matthews, M G O Mullane, R Prentice, M F Stamp, P C Stangeby
More informationTRANSPORT 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 informationUEDGE 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 informationARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS
ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS A. LOARTE, R.D. MONK, J.R. MARTÍN-SOLÍSa,D.J.CAMPBELL, A.V. CHANKIN b, S. CLEMENT, S.J. DAVIES, J. EHRENBERG, S.K. ERENTS c,h.y.guo, P.J. HARBOUR,
More informationINTERMITTENT TURBULENCE AND COHERENT
INTERMITTENT TURBULENCE AND COHERENT STRUCTURES IN LAPD AND ET Troy A. Carter Dept. of Physics and Astronomy, UCLA acknowledgments: D. Pace, B. Brugman, R. Taylor, L. Schmitz, G. Morales, J. Maggs, M.
More informationC-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 informationTH/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 informationDensity Peaking At Low Collisionality on Alcator C-Mod
Density Peaking At Low Collisionality on Alcator C-Mod APS-DPP Meeting Philadelphia, 10/31/2006 M. Greenwald, D. Ernst, A. Hubbard, J.W. Hughes, Y. Lin, J. Terry, S. Wukitch, K. Zhurovich, Alcator Group
More information1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation
1 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation Y. Nakashima1), Y. Higashizono1), H. Kawano1), H. Takenaga2), N. Asakura2), N. Oyama2),
More informationFluctuations and transport in the TCV scrape-off layer
IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY Nucl. Fusion 7 (7) 667 676 NUCLEAR FUSION doi:.88/9-1/7/7/17 Fluctuations and transport in the TCV scrape-off layer O.E. Garcia 1, J. Horacek, R.A.
More informationPedestal 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 informationBlob motion and control. simple magnetized plasmas
Blob motion and control in simple magnetized plasmas Christian Theiler A. Fasoli, I. Furno, D. Iraji, B. Labit, P. Ricci, M. Spolaore 1, N. Vianello 1 Centre de Recherches en Physique des Plasmas (CRPP)
More informationIMPURITY 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 informationCorrelation Between Plasma Rotation and Electron Temperature Gradient Scale Length in LOC/SOC Transition at Alcator C-Mod
Correlation Between Plasma Rotation and Electron Temperature Gradient Scale Length in LOC/SOC Transition at Alcator C-Mod Saeid Houshmandyar 1 W. L. Rowan, 1 P. E. Phillips, 1 M. J. Greenwald, 2 J. W.
More informationElectrode and Limiter Biasing Experiments on the Tokamak ISTTOK
Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK C. Silva, H. Figueiredo, J.A.C. Cabral,, I. Nedzelsky, C.A.F. Varandas Associação Euratom/IST, Centro de Fusão Nuclear, Instituto Superior
More informationScaling 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 informationImpact of neutral atoms on plasma turbulence in the tokamak edge region
Impact of neutral atoms on plasma turbulence in the tokamak edge region C. Wersal P. Ricci, F.D. Halpern, R. Jorge, J. Morales, P. Paruta, F. Riva Theory of Fusion Plasmas Joint Varenna-Lausanne International
More informationDivertor physics research on Alcator C-Mod. B. Lipschultz, B. LaBombard, J.L. Terry, C. Boswell, I.H. Hutchinson
PSFC/JA-05-38 Divertor physics research on Alcator C-Mod B. Lipschultz, B. LaBombard, J.L. Terry, C. Boswell, I.H. Hutchinson Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge
More informationEdge 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 informationInvestigation of Intrinsic Rotation Dependencies in Alcator C-Mod
Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod D. Kwak, A. E. White, J. E. Rice, N. T. Howard, C. Gao, M. L. Reinke, M. Greenwald, C. Angioni, R. M. McDermott, and the C-Mod and ASDEX
More informationImpurity 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 informationDimensionless 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 informationDevelopment 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 information2017 US/EU Transport Task Force Workshop April 26 th 2017 Williamsburg, VA
Pablo Rodriguez-Fernandez 1, A. E. White 1, N. M. Cao 1, A. J. Creely 1, M. J. Greenwald 1, N. T. Howard 1, A. E. Hubbard 1, J. W. Hughes 1, J. H. Irby 1, C. C. Petty 2, J. E. Rice 1 1 Plasma Science and
More informationHighlights from (3D) Modeling of Tokamak Disruptions
Highlights from (3D) Modeling of Tokamak Disruptions Presented by V.A. Izzo With major contributions from S.E. Kruger, H.R. Strauss, R. Paccagnella, MHD Control Workshop 2010 Madison, WI ..onset of rapidly
More informationPlasma shielding during ITER disruptions
Plasma shielding during ITER disruptions Sergey Pestchanyi and Richard Pitts 1 Integrated tokamak code TOKES is a workshop with various tools objects Radiation bremsstrahlung recombination s line s cyclotron
More information