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

Size: px
Start display at page:

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

Transcription

1 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

2 Boundary flows move particles poloidally around the plasma to the divertors. Motivation for boundary flow studies Poloidal motion of entrained impurities macroscopic erosion and redeposition of divertor surfaces co-deposition of tritium. It is difficult to produce a theoretical description of these flows because they are driven in part by anomalous transport. Diverted Tokamak Plasma Γ r LSN Γ Near Sonic Parallel Flows Observed Other reasons for Boundary flow studies: Impurity screening Flow-shear turbulence suppression Core rotation boundary condition Topology-Dependence of H-Mode power threshold Poloidal projection of parallel flows driven by ballooning transport asymmetry in Inner upper and lower single null Divertor Outer Divertor Γ r USN

3 Parallel Mach # toward inner divertor r / a = 1.02 Strong, poloidally asymmetric plasma flows are observed in tokamak boundaries Near-sonic (M ~ 0.5) parallel flow is persistently observed in the High Field Side () SOL (C-Mod [1], JET [2], JT60-U [3]). Outer Divertor --- Position along field line --- Inner Divertor Parallel flow data from Tore Supra imply a strong ballooning-like transport asymmetry, localized within a 30 sector at the low-field side () midplane [4]. What are the contributions of different drive mechanisms? Strong ballooning-like transport asymmetry (transport-driven) Neo-classical Pfirsch-Schlüter flows (drift-driven) Toroidal Rotation (drift-driven) Mechanism that closes flow loop? [1] LaBombard, B. Nucl. Fusion. 44 (2004) [2] Pitts, R.A. J. Nucl. Mater. 337 (2005) [3] Asakura, N. Plasma Phys. Control. Fusion. 44 (2002) [4] Gunn, J.P. J. Nucl. Mater. 363 (2007)

4 C-Mod probes measure total flow vector Midplane Scanning Probe C-Mod s unique array of scanning Langmuir probes provide three localized measurements of total flow vector: Parallel flow from Mach probes, v Midplane Scanning Probe Perpendiuclar flow from potential gradients, v, ExB Radial flow from fluctuation-induced fluxes, v ~~ r, ne θ Vertical Scanning Probe

5 C-Mod probes measure total flow vector Midplane Scanning Probe C-Mod s unique array of scanning Langmuir probes provide three localized measurements of total flow vector: Parallel flow from Mach probes, v Midplane Scanning Probe Perpendiuclar flow from potential gradients, v, ExB Radial flow from fluctuation-induced fluxes, v ~~ r, ne θ Vertical Scanning Probe Net poloidal particle flux can be compared with divertor probes. Inner Divertor Probes Outer Divertor Probes

6 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

7 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

8 Poloidal flow components We start with the hypothesis that the poloidal flow pattern is composed of: A transport-driven part that: Depends on magnetic topology Has finite divergence Γ r v transp

9 Poloidal flow components We start with the hypothesis that the poloidal flow pattern is composed of: A transport-driven part that: Depends on magnetic topology Has finite divergence A drift-driven part that: Depends on field direction Is divergence-free Bx B v drift

10 Poloidal flow components We start with the hypothesis that the poloidal flow pattern is composed of: A transport-driven part that: Depends on magnetic topology Has finite divergence A drift-driven part that: Depends on field direction Is divergence-free We measure: Bx B = Γ r + Bx B A favorable drift direction flow pattern (Bx B towards x-point) : v fav = v transp + v drift

11 Poloidal flow components We start with the hypothesis that the poloidal flow pattern is composed of: A transport-driven part that: Depends on magnetic topology Has finite divergence A drift-driven part that: Depends on field direction Is divergence-free We measure: Bx B = Γ r + Bx B = - Bx B Γ r Bx B A favorable drift direction flow pattern (Bx B towards x-point): v fav = v transp + v drift An unfavorable drift direction flow pattern (Bx B away from x-point): v unfav = v transp v drift

12 Poloidal Flow [km/s] Electron DiamagneticDirection LCFS Poloidal Flow [km/s] Towards Inner Divertor LCFS Transport-driven flow dominant on ; drift-driven on Transport-Driven Part Γ r Transport-Driven Component Bx B Drift-Driven Component LCFS LCFS Parallel, transport-driven flow is dominant on Drift-Driven Part L-mode, 0.8 < n e [10 20 m -3 ] < 1.6. Quantitative analysis shows significant heat convection to inner divertor. Drift-driven flows are dominant on.

13 Poloidal Flow [km/s] Electron DiamagneticDirection LCFS Poloidal Flow [km/s] Towards Inner Divertor LCFS Transport-driven flow dominant on ; drift-driven on Transport-Driven Part Γ r Transport-Driven Component Bx B Drift-Driven Component LCFS LCFS Parallel, transport-driven flow is dominant on Drift-Driven Part.. L-mode, 0.8 < n e [10 20 m -3 ] < 1.6. Quantitative analysis shows significant heat convection to inner divertor. Drift-driven flows are dominant on.

14 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

15 Poloidal Flow [km/s] Electron DiamagneticDirection Drift-driven flow component: / comparison confirms divergence-free flow Calculate total poloidal fluid motion, not guiding center only; includes Parallel Bx B Drift-Driven Component Drift-Driven

16 Poloidal Flow [km/s] Electron DiamagneticDirection Drift-driven flow component: / comparison confirms divergence-free flow Calculate total poloidal fluid motion, not guiding center only; includes Parallel, ExB Bx B Drift-Driven Component Drift-Driven

17 Poloidal Flow [km/s] Electron DiamagneticDirection Drift-driven flow component: / comparison confirms divergence-free flow Calculate total poloidal fluid motion, not guiding center only; includes Parallel, ExB and Diamagnetic flow. Bx B Drift-Driven Drift-Driven Component

18 Poloidal Flow [km/s] Electron DiamagneticDirection Drift-driven flow component: / comparison confirms divergence-free flow Calculate total poloidal fluid motion, not guiding center only; includes Parallel, ExB and Diamagnetic flow. Bx B Drift-Driven Drift-Driven Component

19 nv θ /B θ (Elec Dia) [10 23 T -1 m -2 s -1 ] LCFS Drift-driven flow component: / comparison confirms divergence-free flow Calculate total poloidal fluid motion, not guiding center only; includes Parallel, ExB and Diamagnetic flow. Total drift-driven flow is consistent with divergence-free flow pattern as expected from theory: similar profiles of nv /B to. Measurements confirm (Drift-Driven Flow) = 0 Bx B Drift-Driven Component

20 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

21 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

22 Toroidal rotation and Pfirsch-Schlüter contributions to drift-driven flow unambiguously identified Parallel Flow [km/s] Co-Current Direction B θ φ Bx B Drift-Driven Component We can now unambiguously decompose the drift-driven parallel flow Drift-Driven

23 Toroidal rotation and Pfirsch-Schlüter contributions to drift-driven flow unambiguously identified Parallel Flow [km/s] Co-Current Direction V, ExB (Inferred from Φ) B θ φ Bx B V rot Drift-Driven Component We can now unambiguously decompose the drift-driven parallel flow into toroidal rotation Drift-Driven

24 Toroidal rotation and Pfirsch-Schlüter contributions to drift-driven flow unambiguously identified Parallel Flow [km/s] Co-Current Direction V, ExB (Inferred from Φ) B θ φ Bx B V rot Drift-Driven Component We can now unambiguously decompose the drift-driven parallel flow into toroidal rotation and Pfirsch-Schlüter components. Drift-Driven

25 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

26 transport-driven poloidal flow component consistent with fluctuation-induced radial flux S Γ r Γ r nv θ /B θ Toward Inner Divertor S = 1 S = 0 Transport-Driven Component Model transport-driven poloidal particle flux as sin(θ) on. S: Normalized poloidal distance from outer to inner divertor

27 nv θ [10 21 m -2 s -1 ] LCFS transport-driven poloidal flow component consistent with fluctuation-induced radial flux S Γ r Γ r nv θ /B θ Toward Inner Divertor S = 1 S = 0 Transport-Driven Component Model transport-driven poloidal particle flux as sin(θ) on. Constrain with measured value of poloidal flux on. S: Normalized poloidal distance from outer to inner divertor Measured nv θ

28 nv θ [10 21 m -2 s -1 ] LCFS nv r [10 21 m -2 s -1 ] LCFS Limiter transport-driven poloidal flow component consistent with fluctuation-induced radial flux S Γ r Γ r nv θ /B θ Toward Inner Divertor S = 1 S = 0 Transport-Driven Component Model transport-driven poloidal particle flux as sin(θ) on. Constrain with measured value of poloidal flux on. Calculate radial particle flux implied by poloidal flux using continuity. S: Normalized poloidal distance from outer to inner divertor Measured nv θ Inferred nv r

29 nv θ [10 21 m -2 s -1 ] LCFS nv r [10 21 m -2 s -1 ] LCFS Limiter transport-driven poloidal flow component consistent with fluctuation-induced radial flux S Γ r Γ r nv θ /B θ Toward Inner Divertor S = 1 S = 0 Transport-Driven Component Model transport-driven poloidal particle flux as sin(θ) on. Constrain with measured value of poloidal flux on. Calculate radial particle flux implied by poloidal flux using continuity. S: Normalized poloidal distance from outer to inner divertor Result shows agreement Inferred nv with measurements of r fluctuation-induced particle flux on the through n ~ ~. E Measured nv θ Measured nv r

30 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

31 Outline of talk Flow measurements: Parallel (V ) Perpendicular (V ExB, V P ) Radial (V ~~ r neθ ) Compare upper / lower null discharges Drift-driven components Transport-driven components Consistency check: V θ = 0? Consistency check: V θ + V r = 0? V Pfirsch- Schlüter V Toroidal rotation V Transportdriven Closure of flow loop? Recycling from divertor turbulent inward pinch Volume recombination zone

32 Poloidal flux ratio, divertor/ midplane poloidal particle flux not accounted for at divertor Inner divertor flux is comparable to poloidal particle flux observed at midplane Line-averaged discharge density [10 20 m -3 ]

33 Poloidal flux ratio, divertor/ midplane poloidal particle flux not accounted for at divertor Inner divertor flux is comparable to poloidal particle flux observed at midplane. KN1D simulations [5, 6] indicate that neutral penetration to core/private zone from inner divertor is <10% due to short neutral MFP Line-averaged discharge density [10 20 m -3 ] [5] LaBombard, B. KN1D: A 1-D space, 2-D velocity, kinetic transport algorithm for atomic and molecular hydrogen in an ionizing plasma. Technical report, MIT PSFC, [6] Smick, N., PhD Thesis, MIT (2009)

34 Poloidal flux ratio, divertor/ midplane poloidal particle flux not accounted for at divertor Inner divertor flux is comparable to poloidal particle flux observed at midplane. KN1D simulations [5, 6] indicate that neutral penetration to core/private zone from inner divertor is <10% due to short neutral MFP. Thus, continuity requires that some other mechanism is diverting particles from the SOL. Inner divertor recycling does not explain closure of flow loop Line-averaged discharge density [10 20 m -3 ] [5] LaBombard, B. KN1D: A 1-D space, 2-D velocity, kinetic transport algorithm for atomic and molecular hydrogen in an ionizing plasma. Technical report, MIT PSFC, [6] Smick, N., PhD Thesis, MIT (2009)

35 Hypothesis: turbulent pinch closes flow loop Could particles be returning to the core via a turbulent pinch? This is a solution commonly employed by 2-D edge codes to explain flows. [7, 8, 9] -Γ r? Γ r [7] Pigarov, A.Y. Contrib. Plasma Phys. 48 (2008) [8] Elder, J.D. J. Nucl. Mater (2009) [9] Kirnev, G.S. J. Nucl. Mater. 337 (2005) Ballooning Particle Pinch?

36 Γ r /n e [m/s] Measurements rule out midplane turbulent pinch DIV radial particle flux is robustly zero at midplane location. -Γ r? Γ r DIV Ballooning Particle Pinch?

37 Γ r /n e [m/s] Measurements rule out midplane turbulent pinch DIV X -Γr? Γ r radial particle flux is robustly zero at midplane location. DIV Ballooning Particle Pinch?

38 Γ r /n e [m/s] Measurements rule out midplane turbulent pinch DIV X -Γr? Γ r radial particle flux is robustly zero at midplane location. DIV Caveat: Particle pinch at other locations along the inner divertor leg cannot be ruled out Ballooning Particle Pinch?

39 Hypothesis: Volume recombination closes flow loop Could a volume recombination zone be present in the far SOL of the inner divertor leg, returning particles to the core as neutrals? [10] Γ r Γ n [10] Bonnin, X. J. Nucl. Mater. 313 (2003) Volume Recombination Zone?

40 Hypothesis: Volume recombination closes flow loop Could a volume recombination zone be present in the far SOL of the inner divertor leg, returning particles to the core as neutrals? [10] KN1D modeling indicates recombining plasma would have to impinge on closed field lines to allow sufficient neutral penetration to close loop. Γ r Γ n Volume Recombination Zone? [10] Bonnin, X. J. Nucl. Mater. 313 (2003)

41 LCFS Hypothesis: Volume recombination closes flow loop Could a volume recombination zone be present in the far SOL of the inner divertor leg, returning particles to the core as neutrals? [10] KN1D modeling indicates recombining plasma would have to impinge on closed field lines to allow sufficient neutral penetration to close loop. This is inconsistent with observation of partially attached inner divertor. Neutral penetration from volume recombination zone does not close mass flow loop. Midplane X Midplane Γ n Γ r Attached Detached? [10] Bonnin, X. J. Nucl. Mater. 313 (2003)

42 Future work: Other candidates for closing mass flow loop must be investigated Having eliminated the most obvious closure mechanisms for the poloidal flow loop, we must look to other candidates: Radial convection (E θ x B) X-point specific physics Pinch or diffusion into private flux zone?

43 Conclusions Total flow vector has been measured and shown to be consistent with physical expectations. Measured drift-driven flows are divergence-free. Transport-driven poloidal particle flux is consistent with measured fluctuationinduced radial particle flux. Pfirsch-Schlüter, toroidal rotation and and transport-driven contributions to parallel flow are uniquely identified. Transport-driven parallel flows dominate poloidal particle flux, carrying plasma toward active X-point. Convection is important in poloidal heat transport. Closure mechanism for transport driven flow loop: Divertor recycling cannot account for transport-driven poloidal particle flux. midplane turbulent particle pinch is zero KN1D simulations show that direct neutral penetration from recombining plasma zone does not close the flow loop.

44 References [1] LaBombard, B. Nucl. Fusion. 44 (2004) [2] Pitts, R.A. J. Nucl. Mater. 337 (2005) [3] Asakura, N. Plasma Phys. Control. Fusion. 44 (2002) [4] Gunn, J.P. J. Nucl. Mater. 363 (2007) [5] LaBombard, B. KN1D: A 1-D space, 2-D velocity, kinetic transport algorithm for atomic and molecular hydrogen in an ionizing plasma. Technical report, MIT PSFC, [6] Smick, N., PhD Thesis, MIT (2009) [7] Pigarov, A.Y. Contrib. Plasma Phys. 48 (2008) [8] Elder, J.D. J. Nucl. Mater (2009) [9] Kirnev, G.S. J. Nucl. Mater. 337 (2005) [10] Bonnin, X. J. Nucl. Mater. 313 (2003)

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

Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma

Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters.

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

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

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

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

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

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

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

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

GA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J. GA A27822 THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J. GROEBNER JUNE 2014 DISCLAIMER This report was prepared as an account of work

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

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

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

TH/P4-9. T. Takizuka 1), K. Shimizu 1), N. Hayashi 1), M. Hosokawa 2), M. Yagi 3)

TH/P4-9. T. Takizuka 1), K. Shimizu 1), N. Hayashi 1), M. Hosokawa 2), M. Yagi 3) 1 Two-dimensional Full Particle Simulation of the Flow Patterns in the Scrape-off-layer Plasma for Upper- and Lower- Null Point Divertor Configurations in Tokamaks T. Takizuka 1), K. Shimizu 1), N. Hayashi

More information

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT by M.J. SCHAFFER, J.A. BOEDO, N.H. BROOKS, R.C. ISLER, and R.A. MOYER AUGUST 1998 DISCLAIMER This report was prepared as an account of work

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

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

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

PSI meeting, Aachen Germany, May 2012

PSI 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 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

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

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

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma 1 Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma D. Galassi, P. Tamain, H. Bufferand, C. Baudoin, G. Ciraolo, N. Fedorczak, Ph.

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

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

Impact of neutral atoms on plasma turbulence in the tokamak edge region

Impact 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 information

Links Between Wide Scrape-Off Layers, Large Parallel Flows, and Bursty Transport in Tokamaks

Links Between Wide Scrape-Off Layers, Large Parallel Flows, and Bursty Transport in Tokamaks Links Between Wide Scrape-Off Layers, Large Parallel Flows, and Bursty Transport in Tokamaks J. P. Gunn ), C. Boucher ), M. Dionne ), I. Ďuran 3), V. Fuchs 3), T. Loarer ), I. Nanobashvili ), R. Pánek

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

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

ArbiTER 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 information

Non-local Heat Transport, Core Rotation Reversals and Energy Confinement Saturation in Alcator C-Mod Ohmic L-mode Plasmas

Non-local Heat Transport, Core Rotation Reversals and Energy Confinement Saturation in Alcator C-Mod Ohmic L-mode Plasmas 1 EX/2-2 Non-local Heat Transport, Core Rotation Reversals and Energy Confinement Saturation in Alcator C-Mod Ohmic L-mode Plasmas J.E. Rice 1, M.L. Reinke 1, H.J. Sun 2, P.H. Diamond 3,4, C. Gao 1, N.T.

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

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

1 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 information

A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal. W. M. Stacey

A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal. W. M. Stacey A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal W. M. Stacey Fusion Research Center Georgia Institute of Technology Atlanta, GA 30332, USA October, 2003 ABSTRACT

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

Drive of parallel flows by turbulence and large-scale E B transverse transport in divertor geometry

Drive of parallel flows by turbulence and large-scale E B transverse transport in divertor geometry Drive of parallel flows by turbulence and large-scale E B transverse transport in divertor geometry D Galassi, Patrick Tamain, Hugo Bufferand, G Ciraolo, Philippe Ghendrih, C Baudoin, C Colin, Nicolas

More information

Mean-field and turbulent transport in divertor geometry Davide Galassi

Mean-field and turbulent transport in divertor geometry Davide Galassi Mean-field and turbulent transport in divertor geometry Davide Galassi In collaboration with: Ph. Ghendrih, P. Tamain, C. Baudoin, H. Bufferand, G. Ciraolo, C. Colin and E. Serre Our goal: quantify turbulence

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

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

Modeling of ELM Dynamics for ITER

Modeling of ELM Dynamics for ITER Modeling of ELM Dynamics for ITER A.Y. PANKIN 1, G. BATEMAN 1, D.P. BRENNAN 2, A.H. KRITZ 1, S. KRUGER 3, P.B. SNYDER 4 and the NIMROD team 1 Lehigh University, 16 Memorial Drive East, Bethlehem, PA 18015

More information

Plasma Science and Fusion Center

Plasma 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 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

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

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

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

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

Simulation of Double-Null Divertor Plasmas with the UEDGE Code

Simulation of Double-Null Divertor Plasmas with the UEDGE Code Preprint UCRL-JC-134341 Simulation of Double-Null Divertor Plasmas with the UEDGE Code M. E. Rensink, S. L. Allen, G. 0. Porter, T. 0. Rognlien This article was submitted to 7th International Workshop

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

Shear flows at the tokamak edge and their interaction with edge-localized modes a

Shear flows at the tokamak edge and their interaction with edge-localized modes a PHYSICS OF PLASMAS 14, 056118 2007 Shear flows at the tokamak edge and their interaction with edge-localized modes a A. Y. Aydemir b Institute for Fusion Studies, The University of Texas at Austin, Austin,

More information

ICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks

ICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks ICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks Y. Lin, J.E. Rice, S.J. Wukitch, M.J. Greenwald, A.E. Hubbard, A. Ince- Cushman, L. Lin, E.S. Marmar, M. Porkolab, M.L.

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

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

A 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 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 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

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

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

Spontaneous Core Toroidal Rotation in Alcator C- Mod L-Mode, H-Mode and ITB Plasmas.

Spontaneous Core Toroidal Rotation in Alcator C- Mod L-Mode, H-Mode and ITB Plasmas. PSFC/JA-8-11 Spontaneous Core Toroidal Rotation in Alcator C- Mod L-Mode, H-Mode and ITB Plasmas. Rice, J.E.; Ince-Cushman, A.C.; Reinke, M.L.; Podpaly, Y.; Greenwald, M.J.; LaBombard, B.S.; Marmar, E.S.

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

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

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

Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit. Transport Physics of the Density Limit

Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit. Transport Physics of the Density Limit Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit Transport Physics of the Density Limit R. Hajjar, P. H. Diamond, M. Malkov This research was supported by the U.S. Department of Energy,

More information

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

Innovative Concepts Workshop Austin, Texas February 13-15, 2006 Don Spong Oak Ridge National Laboratory Acknowledgements: Jeff Harris, Hideo Sugama, Shin Nishimura, Andrew Ware, Steve Hirshman, Wayne Houlberg, Jim Lyon Innovative Concepts Workshop Austin, Texas February

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

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U Abstract STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-6U A. SAKASAI, H. TAKENAGA, N. HOSOGANE, H. KUBO, S. SAKURAI, N. AKINO, T. FUJITA, S. HIGASHIJIMA, H. TAMAI, N. ASAKURA, K. ITAMI,

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

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

Divertor physics research on Alcator C-Mod. B. Lipschultz, B. LaBombard, J.L. Terry, C. Boswell, I.H. Hutchinson

Divertor 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 information

Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device

Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device P. T. Bonoli, Y. Lin. S. Shiraiwa, G. M. Wallace, J. C. Wright, and S. J. Wukitch MIT PSFC, Cambridge, MA 02139 59th Annual Meeting

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

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

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

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Concept Overview Implementation on PEGASUS Results Current

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

C-MOD PAC FEBRUARY, 2005 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

C-MOD PAC FEBRUARY, 2005 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER TRANSPORT PROGRAM C-Mod C-MOD PAC FEBRUARY, 2005 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER TRANSPORT IS A BROAD TOPIC WHERE DO WE FOCUS? We emphasize areas where C-Mod - Has unique

More information

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas D. Reiter Institut für Plasmaphysik, FZ-Jülich, Trilateral Euregio Cluster Atomic and Molecular Data for Fusion Energy

More information

Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields

Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields H. Frerichs, O. Schmitz, I. Waters, G. P. Canal, T. E. Evans, Y. Feng and V. Soukhanovskii

More information

Review 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 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 information

Scaling of divertor plasma effectiveness for reducing target-plate heat flux

Scaling of divertor plasma effectiveness for reducing target-plate heat flux Scaling of divertor plasma effectiveness for reducing target-plate heat flux T.D. Rognlien, I. Joseph, G.D. Porter, M.E. Rensink, M.V. Umansky, LLNL S.I. Krasheninnikov & A.Yu. Pigarov, UCSD; M. Groth,

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

DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING

DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING V.S. Chan, S.C. Chiu, Y.A. Omelchenko General Atomics, San Diego, CA, U.S.A. 43rd Annual APS Division of Plasma Physics Meeting

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

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

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

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a)

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 Chang, C.S., 1 Ku, S., 2 Adams M., 3 D Azevedo, G., 4 Chen, Y., 5 Cummings,

More information

On the physics of shear flows in 3D geometry

On the physics of shear flows in 3D geometry On the physics of shear flows in 3D geometry C. Hidalgo and M.A. Pedrosa Laboratorio Nacional de Fusión, EURATOM-CIEMAT, Madrid, Spain Recent experiments have shown the importance of multi-scale (long-range)

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

Effect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade

Effect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade Effect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade 0-29 L. Aho-Mantila a,b *, M. Wischmeier c, K. Krieger c, V. Rohde c, H.W. Müller c, D.P. Coster c, M. Groth

More information

Some 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 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 information

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

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK by T.C. LUCE, J.R. FERRON, C.T. HOLCOMB, F. TURCO, P.A. POLITZER, and T.W. PETRIE GA A26981 JANUARY 2011 DISCLAIMER This report was prepared

More information

Cross-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. 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 information

Simulation of Electric Fields in Small Size Divertor Tokamak Plasma Edge

Simulation of Electric Fields in Small Size Divertor Tokamak Plasma Edge Energ and Power Engineering, 21, 39-45 doi:1.4236/epe.21.217 Published Online Februar 21 (http://www.scirp.org/journal/epe) Simulation of Electric Fields in Small Size Divertor Tokamak Plasma Edge Plasma

More information

Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell

Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell J.M. Canik, L.W. Owen, Y.K.M. Peng, J. Rapp, R.H. Goulding Oak Ridge National Laboratory ORNL is developing a helicon-based

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

INTERMITTENT TURBULENCE AND COHERENT

INTERMITTENT 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 information

Flow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe

Flow 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 information

Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas

Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas Nathan Howard 1 with C. Holland 2, A.E. White 1, M. Greenwald 1, J. Candy 3, P. Rodriguez- Fernandez 1, and

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

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

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

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

Triggering Mechanisms for Transport Barriers

Triggering Mechanisms for Transport Barriers Triggering Mechanisms for Transport Barriers O. Dumbrajs, J. Heikkinen 1, S. Karttunen 1, T. Kiviniemi, T. Kurki-Suonio, M. Mantsinen, K. Rantamäki 1, S. Saarelma, R. Salomaa, S. Sipilä, T. Tala 1 Euratom-TEKES

More information