Expanding Non-Solenoidal Startup with Local Helicity Injection

Size: px
Start display at page:

Download "Expanding Non-Solenoidal Startup with Local Helicity Injection"

Transcription

1 Expanding Non-Solenoidal Startup with Local Helicity Injection Justin M. Perry J. L. Barr, G. M. Bodner, M. W. Bongard, M. G. Burke, R. J. Fonck, E. T. Hinson, B. T. Lewicki, J. A. Reusch, D. J. Schlossberg And the PEGASUS team 56 th Annual Meeting of the APS Division of Plasma Physics University of Wisconsin-Madison Nov. 18, 15 PEGASUS Toroidal Experiment

2 Local Helicity Injection (LHI) is a Promising Non-Solenoidal Startup Technique Ip.18 MA (Iinj = 5 ka) Injected Current Stream. Ip Ip [MA] Local Helicity Injectors. Iinj 25 3 Washer-stack arc sources inject edge current Unstable current streams form tokamak-like state via Taylor relaxation Compact, modular, and appears scalable to MA-class startup

3 'RS'(K,$). ild. e 21 4 artup.! Multi-Year Technology Development has Produced Robust, High Performance Injectors Formidable requirements: E.T. Hinson GP [ms] 35 Gas Feed VPF + VLpA Model for injector impedance 3 ~3x increase in helicity input Veff High Vinj achieved recently Injector Voltage No deleterious PMI Shield Rings cm from LCFS Arc Source High Jinj (~ 1kA/cm2).5 Vinj > 1kV Loop Vo. Cathode Shield VINJ [V] Injection Cathode Fig (a): -D model and!t($ ); (b): -D LHI drive voltages. LHI current drive ~ Vinj Fig Concave injector with PM vs. quiescent frustum shield design Fig Maximum, average &XHY in condition

4 Global Power Balance Model: I p (t) Evolution LHI drive quantified by effective loop voltage:* Power balance relation: I p V LHI A inj B ϕ,inj Ψ Subject to Taylor relaxation current limit:** I p I TL ~ V inj Z [m] Shape Evolution [ ] =. V LHI +V IR +V IND I TF I inj w *: Eidietis et al., J. Fusion Energ. 26, 43 (7) **: Battaglia et al., Nucl. Fusion 51, 7329 (11) Outboard injection à Strong radial compression. R [m] κ: 1 2 δ:.5.5 Net induction voltage dominates current drive System Voltages [V] I p [MA] Taylor Limited 24 V LHI 28 I inj 25 3 V IND -V IR 32 LHI Drive Limited <T e > = 6eV 35 36

5 Detailed Dynamical Model: NIMROD Predicts Current Stream Reconnection as Drive Mechanism Inboard injection, emphasizing LHI current drive over inductive drive 1. Streams follow field lines 2. Adjacent passes attract * J. O Bryan, et al., Physics of Plasmas, 19, 871 (12) 3. Reconnection pinches off current rings 4. Accumulation of poloidal flux; current filaments persist

6 Anomalous Ion Heating Supports Existence of Strong Reconnection Activity T i > T e during LHI T i, LHI >> T i, OH CIII T i [ev] 3 1 LHIOH Handoff T i scales with expectations from reconnection experiments: T i, ~ B2 rec n e ~ I inj V inj Emerging evidence that ion heating is localized to edge HeII T i [ev] 3 1 T perp T See M.G. Burke Poster: GP I bias *(V bias ) 1/2 4 5x1 3

7 Stream Interaction Manifests as Edge Localized MHD Burst MHD bursts accompany I p growth Localized in edge* n=1 line-tied kink structure I p [ka] NIMROD Coherent streams persist in edge, matching NIMROD predictions Auto-Power Auto-Power [p(t)^2/hz] t=18-ms Internal Measurement f=18. khz From (8kHz Bandwidth) Hall Probe R [m] R [m] Injector Radius Suggests reconnection region may be localized to edge ~b [T/s] ~b[mt] PEGASUS * E.T. Hinson, Ph.D. Thesis, UW-Madison, 15.

8 Edge Localized Reconnection and Strong V IND May Support Good Core Confinement, Favorable Scaling Thomson scattering shows strong central peaking T e and pressure profiles Central T e comparable to Ohmic L-mode Contrasts with expectations of highly stochastic field across profile May reflect different drives operating: V IND (across plasma) V LHI (edge) If good confinement persists, scaling to NSTX-U very favorable Need to understand influence of helicity injection vs. inductive drive T e [ev] t shot = 23 ms 4 Approx. R R [cm] Plasma Current [MA] 6 Effect of Confinement Scaling cm Ohmic L-mode 1 Pressure x1 6 [AU] R-R Stochastic Fixed T e =3eV Normalized Helicity Injection Approx. R R [cm] 5 6 8

9 Divertor Injection: Vary Injector Geometry to Separate Inductive and Helicity Drive Effects Fixed plasma geometry à minimal inductive drive Separates effects: edge reconnection Vs. inductive drive HFS à 3-4x increased helicity input Access to higher I p startup Increased B TF test NSTX-U relevant physics New injectors fabricated, ready for install Large aperture, high voltage design Initial tests before Jan 1. I p [ka] Divertor Injectors Projected Injector Performance Past Div Injectors 1 2 7eV 5eV 3eV New Div Injectors V norm = A inj V bias /R inj [V-m] 3 4

10 Building the Physics and Technology Basis for Scalable LHI Increased Performance Injector technology development allows reliable operation at high V inj Suppression of PMI Increased Understanding Experimental evidence supports NIMROD current drive mechanism Outboard injection: reconnection localized to edge, strong inductive drive Thomson Scattering: Ohmic-like core confinement à Favorable scaling to high current startup? Next Steps: studies of confinement and scalability Divertor injectors à increased helicity injection, reduced inductive effects NSTX-U relevant physics regime

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment E. T. Hinson J. L. Barr, M. W. Bongard, M. G. Burke, R. J. Fonck, J. M. Perry, A. J. Redd,

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

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 Non-solenoidal startup using point-source DC helicity injectors

More information

Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup

Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup M.W. Bongard G.M. Bodner, M.G. Burke, R.J. Fonck, J.L. Pachicano, J.M. Perry, C. Pierren, J.A. Reusch, A.T. Rhodes, N.J. Richner, C.

More information

Physics of the Current Injection Process in Localized Helicity Injection

Physics of the Current Injection Process in Localized Helicity Injection Physics of the Current Injection Process in Localized Helicity Injection Edward Thomas Hinson Pegasus Toroidal Experiment University of Wisconsin Madison 57 th American Physical Society Division of Plasma

More information

Non-Solenoidal Startup via Helicity Injection in the PEGASUS ST

Non-Solenoidal Startup via Helicity Injection in the PEGASUS ST Non-Solenoidal Startup via Helicity Injection in the PEGASUS ST M.W. Bongard G.M. Bodner, M.G. Burke, R.J. Fonck, J.L. Pachicano, J.M. Perry, C. Pierren, N.J. Richner, C. Rodriguez Sanchez, D.J. Schlossberg,

More information

Initiatives in Non-Solenoidal Startup and H-mode Physics at Near-Unity A

Initiatives in Non-Solenoidal Startup and H-mode Physics at Near-Unity A Initiatives in Non-Solenoidal Startup and H-mode Physics at Near-Unity A M.W. Bongard, J.L. Barr, M.G. Burke, R.J. Fonck, E.T. Hinson, B.T. Lewicki, J.M. Perry, A.J. Redd, D.J. Schlossberg, K.E. Thome,

More information

Predictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges

Predictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges Predictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges J.L. Barr, M.W. Bongard, M.G. Burke, R.J. Fonck, E.T. Hinson, J.M. Perry, A.J. Redd, D.J. Schlossberg, K.E. Thome

More information

Continuous, Localized Ion Heating due to Magnetic Reconnection in a Low Aspect Ratio Tokamak

Continuous, Localized Ion Heating due to Magnetic Reconnection in a Low Aspect Ratio Tokamak Continuous, Localized Ion Heating due to Magnetic Reconnection in a Low Aspect Ratio Tokamak M. G. Burke, J.L. Barr, M.W. Bongard, R.J. Fonck, E.T. Hinson, J.M. Perry, J.A. Reusch, D.J. Schlossberg EPR

More information

Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST

Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST M.G. Burke, J.L. Barr, M.W. Bongard, R.J. Fonck, E.T. Hinson, J.M. Perry, J.A. Reusch 57 th Annual Meeting of the APS-DPP University

More information

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Aaron J. Redd for the Pegasus Team 2008 Innovative Confinement Concepts Workshop Reno, Nevada June 24-27,

More information

Physics of Intense Electron Current Sources for Helicity Injection

Physics of Intense Electron Current Sources for Helicity Injection Physics of Intense Electron Current Sources for Helicity Injection E.T. Hinson, J.L. Barr, M.W. Bongard, M.G. Burke, R.J. Fonck, B.T. Lewicki, J.M. Perry, A.J. Redd, G.R. Winz APS-DPP 2014 Oct 27-31, 2014

More information

A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg

A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg 51st APS-DPP Annual Meeting November 2-6, 2009 Atlanta, GA USA The PEGASUS Toroidal Experiment Helicity injection in PEGASUS Testing

More information

Non-Solenoidal Plasma Startup in

Non-Solenoidal Plasma Startup in Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique

More information

H-mode and Non-Solenoidal Startup in the Pegasus Ultralow-A Tokamak

H-mode and Non-Solenoidal Startup in the Pegasus Ultralow-A Tokamak 1 OV/5-4 H-mode and Non-Solenoidal Startup in the Pegasus Ultralow-A Tokamak R.J. Fonck 1, J.L. Barr 1, G. M. Bodner 1, M.W. Bongard 1, M.G. Burke 1, D. M. Kriete 1, J.M. Perry 1, J.A. Reusch 1, D.J. Schlossberg

More information

Abstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N

Abstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N Abstract The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N regime (I N > 12). Access to this regime requires a small centerpost

More information

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment 1 EXS/P2-07 Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment R.J. Fonck 1), D.J. Battaglia 2), M.W. Bongard 1), E.T. Hinson 1), A.J. Redd 1), D.J.

More information

Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment

Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment M.W. Bongard, J.L. Barr, M.G. Burke, R.J. Fonck, E.T. Hinson, J.M. Perry, A.J. Redd, D.J. Schlossberg, K.E. Thome

More information

H-mode and ELM Dynamics Studies at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment and their Extension to PEGASUS-Upgrade. M.W.

H-mode and ELM Dynamics Studies at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment and their Extension to PEGASUS-Upgrade. M.W. H-mode and ELM Dynamics Studies at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment and their Extension to PEGASUS-Upgrade M.W. Bongard J.L. Barr, G.M. Bodner, M.G. Burke, R.J. Fonck, H.G. Frerichs,

More information

Initial Investigations of H-mode Edge Dynamics in the PEGASUS Toroidal Experiment

Initial Investigations of H-mode Edge Dynamics in the PEGASUS Toroidal Experiment Initial Investigations of H-mode Edge Dynamics in the PEGASUS Toroidal Experiment M.W. Bongard, R.J. Fonck, K.E. Thome, D.S. Thompson 55 th Annual Meeting of the APS Division of Plasma Physics University

More information

Current Drive Experiments in the HIT-II Spherical Tokamak

Current Drive Experiments in the HIT-II Spherical Tokamak Current Drive Experiments in the HIT-II Spherical Tokamak T. R. Jarboe, P. Gu, V. A. Izzo, P. E. Jewell, K. J. McCollam, B. A. Nelson, R. Raman, A. J. Redd, P. E. Sieck, and R. J. Smith, Aerospace & Energetics

More information

Current Drive Experiments in the Helicity Injected Torus (HIT II)

Current Drive Experiments in the Helicity Injected Torus (HIT II) Current Drive Experiments in the Helicity Injected Torus (HIT II) A. J. Redd, T. R. Jarboe, P. Gu, W. T. Hamp, V. A. Izzo, B. A. Nelson, R. G. O Neill, R. Raman, J. A. Rogers, P. E. Sieck and R. J. Smith

More information

Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus

Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus A. J. Redd Aerospace & Energetics Research University of Washington Seattle, Washington USA 24 Innovative

More information

STATUS OF THE HIT-II EXPERIMENTAL PROGRAM

STATUS OF THE HIT-II EXPERIMENTAL PROGRAM STATUS OF THE HIT-II EXPERIMENTAL PROGRAM Roger J. Smith and the HIT-II Team Plasma Dynamics Group University of Washington, Seattle, Washington HIT-II Team Faculty/Staff Support Staff Graduate Students

More information

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Yasuhiro KAMINOU, Michiaki INOMOTO and Yasushi ONO Graduate School of Engineering, The

More information

Electron Thermal Transport Within Magnetic Islands in the RFP

Electron Thermal Transport Within Magnetic Islands in the RFP Electron Thermal Transport Within Magnetic Islands in the RFP Hillary Stephens University of Wisconsin Madison APS-DPP Meeting November 3, 2009 J.R. Amubel, M.T. Borchardt, D.J. Den Hartog, C.C. Hegna,

More information

Ion Temperature Measurements in the

Ion Temperature Measurements in the Ion Temperature Measurements in the PEGASUS Toroidal Experiment M.G. Burke, M.W. Bongard, R.J. Fonck, D.J. Schlossberg, A.J. Redd 52 nd Annual APS-DPP University of Wisconsin-Madison Chicago, IL November

More information

Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment

Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment (First Evidence of Spheromak Generation and Sustainment) Roger J. Smith Plasma Dynamics Group University of Washington,

More information

1 IC/P4-5. Spheromak Formation by Steady Inductive Helicity Injection

1 IC/P4-5. Spheromak Formation by Steady Inductive Helicity Injection 1 IC/P4-5 Spheromak Formation by Steady Inductive Helicity Injection T. R. Jarboe, C. Akcay, W. T. Hamp, R. Z. Aboul Hosn, G. J. Marklin, B. A. Nelson, R. G. O Neill, P. E. Sieck, R. J. Smith, and J. S.

More information

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment KB Chai Korea Atomic Energy Research Institute/Caltech Paul M.

More information

Spherical Torus Fusion Contributions and Game-Changing Issues

Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus (ST) research contributes to advancing fusion, and leverages on several game-changing issues 1) What is ST? 2) How does research

More information

A Hall Sensor Array for Internal Current Profile Constraint

A Hall Sensor Array for Internal Current Profile Constraint A Hall Sensor Array for Internal Current Profile Constraint M.W. Bongard, R.J. Fonck, B.T. Lewicki, A.J. Redd University of Wisconsin-Madison 18 th Topical Conference on High-Temperature Plasma Diagnostics

More information

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development

More information

Oscillating-Field Current-Drive Experiment on MST

Oscillating-Field Current-Drive Experiment on MST Oscillating-Field Current-Drive Experiment on MST K. J. McCollam, J. K. Anderson, D. J. Den Hartog, F. Ebrahimi, J. A. Reusch, J. S. Sarff, H. D. Stephens, D. R. Stone University of Wisconsin-Madison D.

More information

The RFP: Plasma Confinement with a Reversed Twist

The RFP: Plasma Confinement with a Reversed Twist The RFP: Plasma Confinement with a Reversed Twist JOHN SARFF Department of Physics University of Wisconsin-Madison Invited Tutorial 1997 Meeting APS DPP Pittsburgh Nov. 19, 1997 A tutorial on the Reversed

More information

AC loop voltages and MHD stability in RFP plasmas

AC loop voltages and MHD stability in RFP plasmas AC loop voltages and MHD stability in RFP plasmas K. J. McCollam, D. J. Holly, V. V. Mirnov, J. S. Sar, D. R. Stone UW-Madison 54rd Annual Meeting of the APS-DPP October 29th - November 2nd, 2012 Providence,

More information

Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE

Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE M. Uchida, Y. Nozawa, H. Tanaka, T. Maekawa Graduate School of Energy Science, Kyoto University

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

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

Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS

Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS G. Taylor 1, J.B. Caughman 2, M.D. Carter 2, S. Diem 1, P.C. Efthimion 1, R.W. Harvey 3, J. Preinhaelter 4, J.B. Wilgen 2, T.S. Bigelow 2, R.A.

More information

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak 1 EXS/P2-19 Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak T. Yamada 1), R. Imazawa 2), S. Kamio 1), R. Hihara 1), K. Abe 1), M. Sakumura 1), Q. H. Cao 1), H. Sakakita

More information

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment Derivation of dynamo current drive and stable current sustainment in the HIT SI experiment 1 Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

More information

The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak

The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak H. Furui, Y. Nagashima 2, A. Ejiri, Y. Takase, N. Tsujii, C. Z. Cheng,

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

Evaluation of CT injection to RFP for performance improvement and reconnection studies

Evaluation of CT injection to RFP for performance improvement and reconnection studies Evaluation of CT injection to RFP for performance improvement and reconnection studies S. Masamune A. Sanpei, T. Nagano, S. Nakanobo, R. Tsuboi, S. Kunita, M. Emori, H. Makizawa, H. Himura, N. Mizuguchi

More information

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

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

More information

Abstract. , low-q operating space at near-unity aspect ratio. Plasmas are characterized by high b t ( 20% to date); very low toroidal field (B t

Abstract. , low-q operating space at near-unity aspect ratio. Plasmas are characterized by high b t ( 20% to date); very low toroidal field (B t Abstract The is exploring stability limits in the high b t, low-q operating space at near-unity aspect ratio. Plasmas are characterized by high b t ( 2% to date); very low toroidal field (B t.7 T); densities

More information

REPORT. Numerical Investigation of Transients in the SSPX Spheromak. University of Wisconsin-Madison, Madison, Wisconsin

REPORT. Numerical Investigation of Transients in the SSPX Spheromak. University of Wisconsin-Madison, Madison, Wisconsin UNIVERSITY OF WISCONSIN CENTER FOR PLASMA THEORY AND COMPUTATION REPORT Numerical Investigation of Transients in the SSPX Spheromak C. R. Sovinec, 1 B. I. Cohen, 2 G. A. Cone, 1 E. B. Hooper, 2 and H.

More information

Imposed Dynamo Current Drive

Imposed Dynamo Current Drive Imposed Dynamo Current Drive by T. R. Jarboe, C. Akcay, C. J. Hansen, A. C. Hossack, G. J. Marklin, K. Morgan, B. A. Nelson, D. A. Sutherland, B. S. Victor University of Washington, Seattle, WA 98195,

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

Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal

Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A. Roberds,

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

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta 1 THS/P2-05 KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta Y.S. Park 1), S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), Y.M. Jeon 2), S.H. Hahn 2), N. Eidietis

More information

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation - 15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect

More information

Progress in the Plasma Science and Innovation Center

Progress in the Plasma Science and Innovation Center 1 THP/2-02 Progress in the Plasma Science and Innovation Center U. Shumlak 1, C. Akcay 1, A. H. Glasser 1, C. J. Hansen 1, E. D. Held 2, T. R. Jarboe 1, J.-Y. Ji 2, C. Kim 1, W. Lowrie 1, V. S. Lukin 4,

More information

Fusion Nuclear Science (FNS) Mission & High Priority Research

Fusion Nuclear Science (FNS) Mission & High Priority Research Fusion Nuclear Science (FNS) Mission & High Priority Research Topics Martin Peng, Aaron Sontag, Steffi Diem, John Canik, HM Park, M. Murakami, PJ Fogarty, Mike Cole ORNL 15 th International Spherical Torus

More information

The Effects of Noise and Time Delay on RWM Feedback System Performance

The Effects of Noise and Time Delay on RWM Feedback System Performance The Effects of Noise and Time Delay on RWM Feedback System Performance O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York,

More information

Magnetic Self-Organization in the RFP

Magnetic Self-Organization in the RFP Magnetic Self-Organization in the RFP Prof. John Sarff University of Wisconsin-Madison Joint ICTP-IAEA College on Plasma Physics ICTP, Trieste, Italy Nov 7-18, 2016 The RFP plasma exhibits a fascinating

More information

Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL)

Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL) Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL) 22 nd Topical Meeting on the Technology of Fusion Energy (TOFE) Philadelphia, PA August 22-25, 2016

More information

Current Profile Control by ac Helicity Injection

Current Profile Control by ac Helicity Injection Current Profile Control by ac Helicity Injection Fatima Ebrahimi and S. C. Prager University of Wisconsin- Madison APS 2003 Motivations Helicity injection is a method to drive current in plasmas in which

More information

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

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

More information

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Derek Sutherland HIT-SI Research Group University of Washington July 25, 2017 D.A. Sutherland -- EPR 2017, Vancouver,

More information

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod

More information

Overview of Spherical Tokamak Research in Japan

Overview of Spherical Tokamak Research in Japan OV/5-5 26 th IAEA Fusion Energy Conference Kyoto International Conference Center, Kyoto, Japan, 17-22 Oct. 216 Overview of Spherical Tokamak Research in Japan Y. Takase 1, A. Ejiri 1, T. Fujita 2, N. Fukumoto

More information

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal Effects of stellarator transform on sawtooth oscillations in CTH Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, E.C. Howell, C.A. Johnson, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A.

More information

Simulations of Sawteeth in CTH. Nicholas Roberds August 15, 2015

Simulations of Sawteeth in CTH. Nicholas Roberds August 15, 2015 Simulations of Sawteeth in CTH Nicholas Roberds August 15, 2015 Outline Problem Description Simulations of a small tokamak Simulations of CTH 2 Sawtoothing Sawtoothing is a phenomenon that is seen in all

More information

Flow and dynamo measurements in the HIST double pulsing CHI experiment

Flow and dynamo measurements in the HIST double pulsing CHI experiment Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M.

More information

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is and Stability of Field-Reversed Equilibrium with Toroidal Field Configurations Atomics General Box 85608, San Diego, California 92186-5608 P.O. APS Annual APS Meeting of the Division of Plasma Physics

More information

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

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

More information

CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT

CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT G. Fiksel, 1 A.F. Almagri, 1 J.K. Anderson, 1 T.M. Biewer, 1 D.L. Brower, 2 C-S. Chiang, 1 B.E. Chapman, 1 J.T. Chapman,

More information

Effect of Biasing on Electron Temperature in IR-T1 Tokamak

Effect of Biasing on Electron Temperature in IR-T1 Tokamak Effect of Biasing on Electron Temperature in IR-T1 Tokamak Sakineh Meshkani 1, Mahmood Ghoranneviss 1 and Mansoureh Lafouti 2 1 Plasma Physics Research Center, Science and Research Branch, Islamic Azad

More information

arxiv: v1 [physics.plasm-ph] 24 Nov 2017

arxiv: v1 [physics.plasm-ph] 24 Nov 2017 arxiv:1711.09043v1 [physics.plasm-ph] 24 Nov 2017 Evaluation of ideal MHD mode stability of CFETR baseline scenario Debabrata Banerjee CAS Key Laboratory of Geospace Environment and Department of Modern

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

Behavior of Compact Toroid Injected into the External Magnetic Field

Behavior of Compact Toroid Injected into the External Magnetic Field Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa

More information

Numerical investigation of design and operating parameters on CHI spheromak performance

Numerical investigation of design and operating parameters on CHI spheromak performance Numerical investigation of design and operating parameters on CHI spheromak performance J.B. O Bryan, C.A. Romero-Talamás (University of Maryland, Baltimore County) S. Woodruff, J.E. Stuber, C. Bowman,

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

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

More information

Oscillating Field Current Drive on MST

Oscillating Field Current Drive on MST Oscillating Field Current Drive on MST John Sarff A. Blair, K. McCollam, P. Nonn, J. Anderson, D. Brower 1, D. Craig, B. Deng 1, D. Den Hartog, W. Ding 1, F. Ebrahimi, D. Ennis, G. Fiksel, S. Gangadhara,

More information

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE 1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.

More information

The details of point source helicity injection as a noninductive startup technique must be characterized:

The details of point source helicity injection as a noninductive startup technique must be characterized: The details of point source helicity injection as a noninductive startup technique must be characterized: Is energy confinement dominated by cross-field transport? Is energy confinement dominated by parallel

More information

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

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

More information

Design of the PROTO-SPHERA experiment and of its first step (MULTI-PINCH)

Design of the PROTO-SPHERA experiment and of its first step (MULTI-PINCH) INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 46 (2006) S613 S624 Design of the PROTO-SPHERA experiment and of its first step (MULTI-PINCH) doi:10.1088/0029-5515/46/8/s07

More information

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

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

More information

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

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

More information

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

High Power Heating of Magnetic Reconnection for High-Beta ST Formation in TS-3 and UTST ST Merging Experiments

High Power Heating of Magnetic Reconnection for High-Beta ST Formation in TS-3 and UTST ST Merging Experiments High Power Heating of Magnetic Reconnection for High-Beta ST Formation in TS-3 and UTST ST Merging Experiments Y. Ono, H. Tanabe, Y. Kamino, K. Yamasaki, K. Kadowaki, Y. Hayashi, T. Yamada, C. Z. Cheng

More information

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

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

More information

Measurement and control of the fast ion redistribution on MAST

Measurement and control of the fast ion redistribution on MAST 1 EX/P6-06 Measurement and control of the fast ion redistribution on MAST M. Turnyanskiy 1, C. D. Challis 1, R. J. Akers 1, M. Cecconello 2, D. L. Keeling 1, A. Kirk 1, R. Lake, S. D. Pinches 1,3, S. Sangaroon

More information

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak T.C. Jernigan, L.R. Baylor, S.K. Combs, W.A. Houlberg (Oak Ridge National Laboratory) P.B. Parks (General

More information

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Physics of fusion power. Lecture 14: Anomalous transport / ITER Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities

More information

The Spherical Tokamak as a Compact Fusion Reactor Concept

The Spherical Tokamak as a Compact Fusion Reactor Concept The Spherical Tokamak as a Compact Fusion Reactor Concept R. Kaita Princeton Plasma Physics Laboratory ENN Symposium on Compact Fusion Technologies April 19 20, 2018 *This work supported by US DOE Contract

More information

Active MHD Control Needs in Helical Configurations

Active MHD Control Needs in Helical Configurations Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2, A. Reiman 1, and the W7-AS Team and NBI-Group. 1 Princeton Plasma

More information

Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT-2 Tokamak

Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT-2 Tokamak Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT- Tokamak A.B. Altukhov ), V.V. Bulanin ), V.V. Dyachenko ), L.A. Esipov ), M.V. Gorokhov ), A.D. Gurchenko

More information

Overview of Pilot Plant Studies

Overview of Pilot Plant Studies Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology

More information

Highlights from (3D) Modeling of Tokamak Disruptions

Highlights 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 information

NIMROD Boundary Conditions

NIMROD Boundary Conditions NIMROD Boundary Conditions Carl Sovinec University of Wisconsin-Madison and the Two-Fluid and Transport Group Plasma Science and Innovation Center Annual Meeting Seattle Washington, August 13-14, 2007

More information

Exponential Growth and Filamentary Structure of Nonlinear Ballooning Instability 1

Exponential Growth and Filamentary Structure of Nonlinear Ballooning Instability 1 Exponential Growth and Filamentary Structure of Nonlinear Ballooning Instability 1 Ping Zhu in collaboration with C. C. Hegna and C. R. Sovinec University of Wisconsin-Madison Sherwood Conference Denver,

More information

W.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA

W.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA INTRINSICALLY STEADY STATE TOKAMAKS K.C. SHAING, A.Y. AYDEMIR, R.D. HAZELTINE Institute for Fusion Studies, The University of Texas at Austin, Austin TX 78712 USA W.A. HOULBERG Oak Ridge National Lab.,

More information

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

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

More information

TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER

TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER ITR/P1-16 TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER I. Bandyopadhyay 1), S. Gerhardt 2), S. C. Jardin 2), R.O. Sayer 3), Y. Nakamura 4), S. Miyamoto

More information