Princeton Plasma Physics Laboratory. Multi-mode analysis of RWM feedback with the NMA Code

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

Download "Princeton Plasma Physics Laboratory. Multi-mode analysis of RWM feedback with the NMA Code"

Transcription

1 Princeton Plasma Physics Laboratory Multi-mode analysis of RWM feedback with the NMA Code M. S. Chance, M.Okabayashi, M. S. Chu 12 th Workshop on MHD Stability Control: Improved MHD Control Configurations Columbia University New York, NY Sunday, November 18 Tuesday, November 20, 2007 Work supported by U.S. Department of Contract No. DE-AC02-76-CH03073.

2 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Introduction The nma code utilizes the full spectrum of mhd modes from dcon. With the resisitve shell included, a complete set of open loop (without feedback) eigenfunctions are calculated from energy integrals that include the dissipation in the shell. These eigenmodes can have varying helicities, both positive and negative. They are included as circuit elements in the circuit equations that describes the feedback process. We have calculated the effects of a variety of feedback coil configurations on iter relevant equilibria, examining the mode structures before, and after the stabilization of the rwm. The efficiency of the feedback depends strongly on the phasing of the coils with respect to each other, and to the rwm. The efficiency is also dependent on the interaction of the modes with each other. The RWM is deformed (non-rigid) during the feedback process. Stable modes can perhaps be driven by imperfect coils. Experimental demonstration of these effects could be interesting.

3 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Normal Mode Approach to Feedback Stabilization of the RWM is based on the Extended Principle W p + K + W v +D w + E c = 0 Perturbed Plasma Kinetic Perturbed Vacuum Dissipation in Resistive Wall Input from External Coil General static plasma equilibrium Chu, Chance, Glasser, Okabayashi, NF, 43, 441 (2003) General external modes W ithout feedback, the energy principle is reduced to the self-adjoint expression W p + K + W v +D w + E c = 0 Perturbed Plasma DCON Perturbed Vacuum VACUUM Dissipation in Resistive Wall Tank A set of normal modes can satisfy this relationship and they are the the open loop eigenfunctions (R W Ms) 3 chu ITPA Meeting 2007

4 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, A set of Equilibria in ITER Geometry Studied with an up-down Symmeterized Approximate Wall A Set of Equilibira Studied with an up-down Symmetrized Approximate Wall ITLocation E R and Double (L iu) Open Wall Loop Growth Rates Plasma Z A pproximate Symmetrized Wall 4 R The wall is an up-down symmetric approximation to the inner wall of the iter wall structure. The open-loop growth rates computed by the nma code agree with those obtained by mars-f.

5 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Example of the open Loop Eigenfunction (the Resistive Wall Mode) in ITER T he original proposed (Gribov) coil geometry relative to the plasma is similar to C-Coil (Gribov, private communication) 5 chu

6 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, The Coils External to the Plasma Excite the RWM s Through the Feedback Logic Amplitude of RWM Open-L oop Growth R ate E xcitation Matrix Coil Current T ime Constant of Coils i t I c t + I c c i i = = G c l l Gain Matrix c I c E i c F c l ({ i}, { I c }) Sensor Matrix With feedback, the growth rate is then determined by D(s) = si E GF (s + 1 )I c 6

7 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Plasma Wall Geometry and Coil Set Models External Port Coils ( ) ( ) 36 E xternal Coils (not yet studied) Z(m) Internal Port Coils ( )( ) ( )( ) Original Gribov Proposal ( ) ( ) Internal B lanket Coils ( ) ( ) ( ) ( ) R(m) 9 chu ITPA Meeting 2007

8 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Typical Gain vs. Phase Behavior Modeling RWM Experiments with NMA We have used the NMA code to calculate the marginal gain versus the phasing of the feedback coils that is needed to stabilize the RWM in the ITER device. marginal gain Mid_plane coil only with off_midplane The mid-plane coil is optimized to the mode here off_midplane coil toroidal phase (rad)

9 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Mode Structures We have also looked at the mode pattern on the resistive shell with and without the feedback, showing the mode deformation due to the coils Bn pattern on the plasma surface Mid_plane coil only at marginal gain (g=6) Mid_plane coil + Off_midplane at marginal gain (g=10) poloidal direction top Eigenmode no-feedback bottom toroidal direction

10 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Effect of Phase Mismatch to the RWM - RWM Feedkack with with Mid-Plane Coil-only (ITER port-plug)- Interaction between Normal RWM and Shallow Stable Branches Destabilzes Overall Feedback when the Feedback Phase Slipps Feedback phase at optimized location Feedback phase -62 deg shift Feedback phase shift -72 deg shift Normal RWM 0.0 Negative Helicity branch Other stable branches Stable Negative Helicity branch remains stable Negative Helicity branch acts as the positive feedback in phase relation and becomes unstable /u3/okabay/mm_code/iter.30b_all/iter.30b_c_w/090

11 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Modes Coupling with the C-coil # 199: RWM Mode non-rigidity in low/high rotation plasmas (M. Chance, M. Chu,A. Garofalo..) growth rate ITER Mid-PLANE COIL RWM FEEDBACK - The mode-coil phase mismatch requires higher gain. The negative helicity mode contribution is inhibitive 0 φ= gain Mode pattern on plasma surface tor. angle normal RWM branch coupled with Negative helicity branch φ (degrees) : Coil pattern toroidal shift relative to the optimized toroidal coil geometry pol. angle

12 Multimode analysis of RWM feedback with the NMA code Columbia University, New York, NY, November 18 20, Conclusions The efficiency of the feedback depend strongly on the phasing of the coils with respect to each other and to the rwm. The efficiency is also dependent on the interaction of the modes with each other. The RWM is deformed (non-rigid) during the feedback process. This can be minimized by optimizing the coupling to the rwm Stable modes can perhaps be excited by imperfect coils and overdriving the feedback system. Experimental demonstration of these effects could be interesting.

RWM Control in FIRE and ITER

RWM Control in FIRE and ITER RWM Control in FIRE and ITER Gerald A. Navratil with Jim Bialek, Allen Boozer & Oksana Katsuro-Hopkins MHD Mode Control Workshop University of Texas-Austin 3-5 November, 2003 OUTLINE REVIEW OF VALEN MODEL

More information

Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance

Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance M.Okabayashi, M. Chance, M. Chu* and R. Hatcher A. Garofalo**, R. La Haye*, H. Remeirdes**, T. Scoville*, and T.

More information

Resistive Wall Mode Control in DIII-D

Resistive Wall Mode Control in DIII-D Resistive Wall Mode Control in DIII-D by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil

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

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS RESISTIVE WALL MODE STABILIZATION RESEARCH ON STATUS AND RECENT RESULTS by A.M. Garofalo1 in collaboration with J. Bialek,1 M.S. Chance,2 M.S. Chu,3 T.H. Jensen,3 L.C. Johnson,2 R.J. La Haye,3 G.A. Navratil,1

More information

Effects of Noise in Time Dependent RWM Feedback Simulations

Effects of Noise in Time Dependent RWM Feedback Simulations Effects of Noise in Time Dependent RWM Feedback Simulations O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York, NY USA) Building

More information

Requirements for Active Resistive Wall Mode (RWM) Feedback Control

Requirements for Active Resistive Wall Mode (RWM) Feedback Control Requirements for Active Resistive Wall Mode (RWM) Feedback Control Yongkyoon In 1 In collaboration with M.S. Chu 2, G.L. Jackson 2, J.S. Kim 1, R.J. La Haye 2, Y.Q. Liu 3, L. Marrelli 4, M. Okabayashi

More information

DIII D. by M. Okabayashi. Presented at 20th IAEA Fusion Energy Conference Vilamoura, Portugal November 1st - 6th, 2004.

DIII D. by M. Okabayashi. Presented at 20th IAEA Fusion Energy Conference Vilamoura, Portugal November 1st - 6th, 2004. Control of the Resistive Wall Mode with Internal Coils in the Tokamak (EX/3-1Ra) Active Measurement of Resistive Wall Mode Stability in Rotating High Beta Plasmas (EX/3-1Rb) by M. Okabayashi Presented

More information

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER GA A24759 RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER by A.M. GAROFALO, J. BIALEK, M.S. CHANCE, M.S. CHU, D.H. EDGELL, G.L. JACKSON, T.H. JENSEN, R.J.

More information

RWM Control Code Maturity

RWM Control Code Maturity RWM Control Code Maturity Yueqiang Liu EURATOM/CCFE Fusion Association Culham Science Centre Abingdon, Oxon OX14 3DB, UK Work partly funded by UK EPSRC and EURATOM. The views and opinions expressed do

More information

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations Dynamical plasma response of resistive wall modes to changing external magnetic perturbations M. Shilov, C. Cates, R. James, A. Klein, O. Katsuro-Hopkins, Y. Liu, M. E. Mauel, D. A. Maurer, G. A. Navratil,

More information

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a

Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a PHYSICS OF PLASMAS VOLUME 11, NUMBER 5 MAY 2004 Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a M. Shilov, b) C. Cates, R. James, A. Klein, O. Katsuro-Hopkins,

More information

Disruption dynamics in NSTX. long-pulse discharges. Presented by J.E. Menard, PPPL. for the NSTX Research Team

Disruption dynamics in NSTX. long-pulse discharges. Presented by J.E. Menard, PPPL. for the NSTX Research Team Disruption dynamics in NSTX long-pulse discharges Presented by J.E. Menard, PPPL for the NSTX Research Team Workshop on Active Control of MHD Stability: Extension of Performance Monday, November 18, 2002

More information

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI by J.M. HANSON, F. TURCO M.J. LANCTOT, J. BERKERY, I.T. CHAPMAN, R.J. LA HAYE, G.A. NAVRATIL, M. OKABAYASHI, H. REIMERDES, S.A. SABBAGH,

More information

Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas

Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas J. P. Levesque April 12, 2011 1 Outline Basic Resistive Wall Mode (RWM) model RWM stability, neglecting kinetic effects Sufficient for

More information

Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas *

Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas * 1 EX/P8-07 Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas * J.W. Berkery 1, S.A. Sabbagh 1, A. Balbaky 1, R.E. Bell 2, R. Betti 3, J.M. Bialek 1, A. Diallo 2, D.A.

More information

Plasma Response Control Using Advanced Feedback Techniques

Plasma Response Control Using Advanced Feedback Techniques Plasma Response Control Using Advanced Feedback Techniques by M. Clement 1 with J. M. Hanson 1, J. Bialek 1 and G. A. Navratil 1 1 Columbia University Presented at 59 th Annual APS Meeting Division of

More information

GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS

GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS by M. OKABAYASHI, I.N. BOGATU, T. BOLZONELLA, M.S. CHANCE, M.S. CHU, A.M. GAROFALO, R. HATCHER, Y. IN, G.L. JACKSON,

More information

Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research

Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research 1 TH/P9-10 Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research S. Günter, M. Garcia-Munoz, K. Lackner, Ph. Lauber, P. Merkel, M. Sempf, E. Strumberger, D. Tekle and

More information

Modeling of active control of external magnetohydrodynamic instabilities*

Modeling of active control of external magnetohydrodynamic instabilities* PHYSICS OF PLASMAS VOLUME 8, NUMBER 5 MAY 2001 Modeling of active control of external magnetohydrodynamic instabilities* James Bialek, Allen H. Boozer, M. E. Mauel, and G. A. Navratil Department of Applied

More information

Supported by. Role of plasma edge in global stability and control*

Supported by. Role of plasma edge in global stability and control* NSTX Supported by College W&M Colorado Sch Mines Columbia U CompX General Atomics INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U

More information

MAGNETIC FIELD ERRORS: RECONCILING MEASUREMENT, MODELING AND EMPIRICAL CORRECTIONS ON DIII D

MAGNETIC FIELD ERRORS: RECONCILING MEASUREMENT, MODELING AND EMPIRICAL CORRECTIONS ON DIII D MAGNETIC FIELD ERRORS: RECONCILING MEASUREMENT, MODELING AND EMPIRICAL CORRECTIONS ON DIII D by M.J. Schaffer, T.E. Evans, J.L. Luxon, G.L. Jackson, J.A. Leuer, J.T. Scoville Paper QP1.76 Presented at

More information

Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas

Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas 1 EX/5-3Ra Effect of Resonant and Non-resonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas H. Reimerdes 1), A.M. Garofalo 2), E.J. Strait 2), R.J. Buttery 3), M.S. Chu 2), Y. In 4),

More information

Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Frequency

Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Frequency Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Freuency by M.S. Chu In collaboration with L.L. Lao, M.J. Schaffer, T.E. Evans E.J. Strait (General Atomics)

More information

STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK

STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK GA A24014 STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK by M. Okabayashi, J. Bialek, M.S. Chance, M.S. Chu, E.D. Fredrickson, A.M. Garofalo, R. Hatcher, T.H.

More information

Modeling of resistive wall mode and its control in experiments and ITER a

Modeling of resistive wall mode and its control in experiments and ITER a Modeling of resistive wall mode and its control in experiments and ITER a Yueqiang Liu b Department of Applied Mechanics, EURATOM/VR Fusion Association, Chalmers University of Technology, Göteborg, Sweden

More information

Plasma Stability in Tokamaks and Stellarators

Plasma Stability in Tokamaks and Stellarators Plasma Stability in Tokamaks and Stellarators Gerald A. Navratil GCEP Fusion Energy Workshop Princeton, NJ 1- May 006 ACKNOWLEDGEMENTS Borrowed VGs from many colleagues: J. Bialek, A. Garofalo,R. Goldston,

More information

Effect of an error field on the stability of the resistive wall mode

Effect of an error field on the stability of the resistive wall mode PHYSICS OF PLASMAS 14, 022505 2007 Effect of an error field on the stability of the resistive wall mode Richard Fitzpatrick Institute for Fusion Studies, Department of Physics, University of Texas at Austin,

More information

GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS

GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS by H. REIMERDES, A.M. GAROFALO, E.J. STRAIT, R.J. BUTTERY, M.S. CHU, Y. In, G.L. JACKSON, R.J.

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

Is the Troyon limit a beta limit?

Is the Troyon limit a beta limit? Is the Troyon limit a beta limit? Pierre-Alexandre Gourdain 1 1 Extreme State Physics Laboratory, Department of Physics and Astronomy, University of Rochester, Rochester, NY 14627, USA The plasma beta,

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

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

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

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.

More information

Resistive wall mode stabilization by slow plasma rotation in DIII-D tokamak discharges with balanced neutral beam injection a

Resistive wall mode stabilization by slow plasma rotation in DIII-D tokamak discharges with balanced neutral beam injection a PHYSICS OF PLASMAS 14, 056101 2007 Resistive wall mode stabilization by slow plasma rotation in DIII-D tokamak discharges with balanced neutral beam injection a E. J. Strait, b A. M. Garofalo, c G. L.

More information

Resistive Wall Mode Stabilization and Plasma Rotation Damping Considerations for Maintaining High Beta Plasma Discharges in NSTX

Resistive Wall Mode Stabilization and Plasma Rotation Damping Considerations for Maintaining High Beta Plasma Discharges in NSTX 1 EXS/5-5 Resistive Wall Mode Stabilization and Plasma Rotation Damping Considerations for Maintaining High Beta Plasma Discharges in NSTX S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), R.E. Bell ),

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

Analytical Study of RWM Feedback Stabilisation with Application to ITER

Analytical Study of RWM Feedback Stabilisation with Application to ITER CT/P- Analytical Study of RWM Feedback Stabilisation with Application to ITER Y Gribov ), VD Pustovitov ) ) ITER International Team, ITER Naka Joint Work Site, Japan ) Nuclear Fusion Institute, Russian

More information

Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U *

Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U * 1 EX/P4-34 Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U * J.W. Berkery 1, S.A. Sabbagh 1, Y.S. Park 1, R.E. Bell 2, S.P. Gerhardt 2, C.E. Myers 2 1 Department of

More information

Advances in Global MHD Mode Stabilization Research on NSTX

Advances in Global MHD Mode Stabilization Research on NSTX 1 EX/5-1 Advances in Global MHD Mode Stabilization Research on NSTX S.A. Sabbagh 1), J.W. Berkery 1), R.E. Bell 2), J.M. Bialek 1), S.P. Gerhardt 2), J.E. Menard 2), R. Betti 3), D.A. Gates 2), B. Hu 3),

More information

Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift )

Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift ) Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift ) Shoichi OKAMURA 1,2) 1) National Institute for Fusion Science, Toki 509-5292, Japan 2) Department of Fusion Science,

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

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

Introduction to Fusion Physics

Introduction to Fusion Physics Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction

More information

MHD. Jeff Freidberg MIT

MHD. Jeff Freidberg MIT MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium

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

Active and Passive MHD Spectroscopy on Alcator C-Mod

Active and Passive MHD Spectroscopy on Alcator C-Mod Active and Passive MHD Spectroscopy on Alcator C-Mod J A Snipes, D A Schmittdiel, C Boswell, A Fasoli *, W Burke, R S Granetz, R R Parker, S Sharapov #, R Vieira MIT Plasma Science and Fusion Center, Cambridge,

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

- 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

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system J.M. Ané 1, V. Grandgirard, F. Albajar 1, J.Johner 1 1Euratom-CEA Association, Cadarache, France Euratom-EPFL

More information

INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS

INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS A.D. Turnbull and L.L. Lao General Atomics (with contributions from W.A. Cooper and R.G. Storer) Presentation

More information

Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Afvén Frequency

Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Afvén Frequency 1 THS/P5-04 Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Afvén Frequency M.S. Chu, 1 L.L. Lao, 1, M.J. Schaffer 1 T.E. Evans, 1 E.J. Strait, 1 Y.Q. Liu 2, M.J.

More information

The Status of the Design and Construction of the Columbia Non-neutral Torus

The Status of the Design and Construction of the Columbia Non-neutral Torus The Status of the Design and Construction of the Columbia Non-neutral Torus J. P. Kremer,T.S.Pedersen,N.Pomphrey,W.Reiersen and F. Dahlgren Dept. of Applied Physics and Applied Mathematics, Columbia University,

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

Macroscopic Stability

Macroscopic Stability Macroscopic Stability FESAC Facilities Panel Meeting June 13, 2005 E. S. Marmar for the Alcator Group Unique C-Mod Properties Guide MHD Research Program High field, high current density, compact size,

More information

Control of linear modes in cylindrical resistive MHD with a resistive wall, plasma rotation, and complex gain

Control of linear modes in cylindrical resistive MHD with a resistive wall, plasma rotation, and complex gain Control of linear modes in cylindrical resistive MHD with a resistive wall, plasma rotation, and complex gain Dylan Brennan 1 and John Finn 2 contributions from Andrew Cole 3 1 Princeton University / PPPL

More information

A New Resistive Response to 3-D Fields in Low Rotation H-modes

A New Resistive Response to 3-D Fields in Low Rotation H-modes in Low Rotation H-modes by Richard Buttery 1 with Rob La Haye 1, Yueqiang Liu 2, Bob Pinsker 1, Jong-kyu Park 3, Holger Reimerdes 4, Ted Strait 1, and the DIII-D research team. 1 General Atomics, USA 2

More information

Reversed Field Pinch: basics

Reversed Field Pinch: basics Reversed Field Pinch: basics Piero Martin Consorzio RFX- Associazione Euratom-ENEA sulla fusione, Padova, Italy Department of Physics, University of Padova Notes for the lecture at the European Ph.D. Course

More information

CSA$-9 k067s-~ STUDY OF THE RESISTIVE WALL MODE IN DIII-D GAMA22921 JULY 1998

CSA$-9 k067s-~ STUDY OF THE RESISTIVE WALL MODE IN DIII-D GAMA22921 JULY 1998 STUDY OF THE RESISTIVE WALL MODE IN DIIID GAMA22921 CSA$9 k067s~ by A.M. GAROFALO, J. BIALEK, M.S. CHU, E.D. FREDRICKSON, R.J. GROEBNER, R.J. La HAYE, L.L. LAO, G.A. NAVRATIL, B.W. RICE, S.A. SABBAGH,

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

(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time

(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time Studies of Spherical Tori, Stellarators and Anisotropic Pressure with M3D 1 L.E. Sugiyama 1), W. Park 2), H.R. Strauss 3), S.R. Hudson 2), D. Stutman 4), X-Z. Tang 2) 1) Massachusetts Institute of Technology,

More information

Experimental Vertical Stability Studies for ITER Performance and Design Guidance

Experimental Vertical Stability Studies for ITER Performance and Design Guidance 1 IT/2-4Rb Experimental Vertical Stability Studies for ITER Performance and Design Guidance D.A. Humphreys 1), T.A. Casper 2), N. Eidietis 1), M. Ferrara 3), D.A. Gates 4), I.H. Hutchinson 3), G.L. Jackson

More information

NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997

NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997 NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU General Atomics Nimrod Project Review Meeting July 21 22, 1997 Work supported by the U.S. Department of Energy under Grant DE-FG03-95ER54309 and Contract

More information

Local organizer. National Centralized Tokamak

Local organizer. National Centralized Tokamak US/Japan Workshop on MHD Stability Control and Related Confinement of Toroidal Plasmas, 6-8 February 2006, JAEA-Naka, Japan with ITPA meeting of MHD Topical Group, 6-9 February Venue and Dates The workshop

More information

Princeton Plasma Physics Laboratory

Princeton Plasma Physics Laboratory Princeton Plasma Physics Laboratory PPPL-4239 PPPL-4239 Computation of Three Dimensional Tokamak and Spherical Torus Equilibria Jong-kyu Park, Allen H. Boozer, and Alan H. Glasser (Preprint) May 27 Prepared

More information

Progress in Modeling of ARIES ACT Plasma

Progress in Modeling of ARIES ACT Plasma Progress in Modeling of ARIES ACT Plasma And the ARIES Team A.D. Turnbull, R. Buttery, M. Choi, L.L Lao, S. Smith, General Atomics H. St John, G. Staebler C. Kessel Princeton Plasma Physics Laboratory

More information

Numerical Method for the Stability Analysis of Ideal MHD Modes with a Wide Range of Toroidal Mode Numbers in Tokamaks

Numerical Method for the Stability Analysis of Ideal MHD Modes with a Wide Range of Toroidal Mode Numbers in Tokamaks Numerical Method for the Stability Analysis of Ideal MHD Modes with a Wide Range of Toroidal Mode Numbers in Tokamaks Nobuyuki AIBA, Shinji TOKUDA, Takaaki FUJITA, Takahisa OZEKI, Ming S. CHU 1), Philip

More information

Robust control of resistive wall modes using pseudospectra

Robust control of resistive wall modes using pseudospectra Robust control of resistive wall modes using pseudospectra M. Sempf, P. Merkel, E. Strumberger, C. Tichmann, and S. Günter Max-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany GOTiT

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

GA A23922 ITER-FEAT PHYSICS STUDY ADVANCED TOKAMAK (AT) OPERATION CY01 IR&D PROJECT

GA A23922 ITER-FEAT PHYSICS STUDY ADVANCED TOKAMAK (AT) OPERATION CY01 IR&D PROJECT GA A9 ITER-FEAT PHYSICS STUDY ADVANCED TOKAMAK (AT) OPERATION CY IR&D PROJECT by VS CHAN, MS CHU, TE EVANS, DA HUMPHREYS, LL LAO, JA LEUER, TE PETRIE, GM STAEBLER, PB SNYDER, HE ST JOHN, and AD TURNBULL

More information

INTERACTION OF AN EXTERNAL ROTATING MAGNETIC FIELD WITH THE PLASMA TEARING MODE SURROUNDED BY A RESISTIVE WALL

INTERACTION OF AN EXTERNAL ROTATING MAGNETIC FIELD WITH THE PLASMA TEARING MODE SURROUNDED BY A RESISTIVE WALL INTERACTION OF AN EXTERNAL ROTATING MAGNETIC FIELD WITH THE PLASMA TEARING MODE SURROUNDED BY A RESISTIVE WALL S.C. GUO* and M.S. CHU GENERAL ATOMICS *Permanent Address: Consorzio RFX, Padova, Italy **The

More information

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University

More information

Thin Faraday foil collectors as a lost ion diagnostic

Thin Faraday foil collectors as a lost ion diagnostic Thin Faraday foil collectors as a lost ion diagnostic F.E. Cecil Colorado School of Mines D.S. Darrow and R. Ellis Princeton Plasma Physics Lab W.W. Heidbrink University of California, Irvine V. Kiptily

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

Plasma models for the design of the ITER PCS

Plasma models for the design of the ITER PCS Plasma models for the design of the ITER PCS G. De Tommasi 1,2 on behalf of the CREATE team 1 Consorzio CREATE, Naples, Italy 2 Department of Electrical Engineering and Information Technology, University

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

Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain

Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain arxiv:146.5245v1 [physics.plasm-ph] 2 Jun 214 D. P. Brennan and J. M. Finn June 23, 214 Department of Astrophysical

More information

Sawteeth in Tokamaks and their relation to other Two-Fluid Reconnection Phenomena

Sawteeth in Tokamaks and their relation to other Two-Fluid Reconnection Phenomena Sawteeth in Tokamaks and their relation to other Two-Fluid Reconnection Phenomena S. C. Jardin 1, N. Ferraro 2, J. Chen 1, et al 1 Princeton Plasma Physics Laboratory 2 General Atomics Supported by the

More information

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li Axisymmetric Tandem Mirrors: Stabilization and Confinement Studies R. F. Post, T. K. Fowler*, R. Bulmer, J. Byers, D. Hua, L. Tung Lawrence Livermore National Laboratory *Consultant, Presenter This talk

More information

Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak

Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak M. Garcia-Munoz, S. E. Sharapov, J. Ayllon, B. Bobkov, L. Chen, R. Coelho, M. Dunne, J. Ferreira, A. Figueiredo, M. Fitzgerald, J. Galdon-Quiroga,

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

Identication of Multi-Modal Plasma Responses to Applied Magnetic Perturbations using the Plasma Reluctance

Identication of Multi-Modal Plasma Responses to Applied Magnetic Perturbations using the Plasma Reluctance Identication of Multi-Modal Plasma Responses to Applied Magnetic Perturbations using the Plasma Reluctance Nikolas C. Logan 1, Carlos Paz-Soldan 2, Jong-Kyu Park 1, Ra Nazikian 1 1 Princeton Plasma Physics

More information

Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter

Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Matthias Hölzl Nonlinear ELM Simulations DPG Spring Meeting, Jena, 02/2013

More information

Design of structural components and radial-build for FFHR-d1

Design of structural components and radial-build for FFHR-d1 Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies with participations from China and Korea February 26-28, 2013 at Kyoto University in Uji, JAPAN 1 Design of structural components

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

MHD Linear Stability Analysis Using a Full Wave Code

MHD Linear Stability Analysis Using a Full Wave Code US-Japan JIFT Workshop on Progress of Extended MHD Models NIFS, Toki,Japan 2007/03/27 MHD Linear Stability Analysis Using a Full Wave Code T. Akutsu and A. Fukuyama Department of Nuclear Engineering, Kyoto

More information

Predictive Simulation of Global Instabilities in Tokamaks

Predictive Simulation of Global Instabilities in Tokamaks Predictive Simulation of Global Instabilities in Tokamaks Stephen C. Jardin Princeton Plasma Physics Laboratory Fourth ITER International Summer School IISS 2010 Institute of Fusion Studies University

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

Feedback stabilization of the resistive shell mode in a tokamak fusion reactor

Feedback stabilization of the resistive shell mode in a tokamak fusion reactor Feedback stabilization of the resistive shell mode in a tokamak fusion reactor Institute for Fusion Studies, Department of Physics, The University of Texas at Austin, Austin, Texas 78712 Received 16 September

More information

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D by A. WINGEN, N.M. FERRARO, M.W. SHAFER, E.A. UNTERBERG, T.E. EVANS, D.L. HILLIS, and P.B. SNYDER JULY 2014 DISCLAIMER This report was

More information

DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS

DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS GA A25808 DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS by D.A. HUMPHREYS, J.R. FERRON, A.W. HYATT, R.J. La HAYE, J.A. LEUER, B.G. PENAFLOR, M.L. WALKER, A.S. WELANDER,

More information

Magnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria

Magnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria Magnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria Robert G. Kleva Institute for Plasma Research, University of Maryland, College Park, Maryland

More information

ELMs and Constraints on the H-Mode Pedestal:

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

More information

NIMROD simulations of dynamo experiments in cylindrical and spherical geometries. Dalton Schnack, Ivan Khalzov, Fatima Ebrahimi, Cary Forest,

NIMROD simulations of dynamo experiments in cylindrical and spherical geometries. Dalton Schnack, Ivan Khalzov, Fatima Ebrahimi, Cary Forest, NIMROD simulations of dynamo experiments in cylindrical and spherical geometries Dalton Schnack, Ivan Khalzov, Fatima Ebrahimi, Cary Forest, 1 Introduction Two experiments, Madison Plasma Couette Experiment

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 A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS by T.C. LUCE, G.L. JACKSON, T.W. PETRIE, R.I. PINSKER, W.M. SOLOMON, F. TURCO, N. COMMAUX, J.R. FERRON, A.M. GAROFALO,

More information

Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling

Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling 1 TH/P1-18 Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling T. Bolzonella 1, P. Bettini 1, L. Figini 2, S.C. Guo 1, Y.Q. Liu 3, G. Marchiori 1, G. Matsunaga 4,

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

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