Halo Current and Resistive Wall Simulations of ITER H.R. Strauss 1, Linjin Zheng 2, M. Kotschenreuther 2, W.Park 3, S. Jardin 3, J. Breslau 3, A.Pletzer.

Slides:



Advertisements
Similar presentations
Dynamo Effects in Laboratory Plasmas S.C. Prager University of Wisconsin October, 2003.
Advertisements

Reconnection: Theory and Computation Programs and Plans C. C. Hegna Presented for E. Zweibel University of Wisconsin CMSO Meeting Madison, WI August 4,
November 3-5, 2003Feedback Workshop, Austin NORMAL MODE APPROACH TO MODELING OF FEEDBACK STABILIZATION OF THE RESISTIVE WALL MODE By M.S. Chu(GA), M.S.
Particle acceleration in a turbulent electric field produced by 3D reconnection Marco Onofri University of Thessaloniki.
Simulations of the core/SOL transition of a tokamak plasma Frederic Schwander,Ph. Ghendrih, Y. Sarazin IRFM/CEA Cadarache G. Ciraolo, E. Serre, L. Isoardi,
Lecture Series in Energetic Particle Physics of Fusion Plasmas Guoyong Fu Princeton Plasma Physics Laboratory Princeton University Princeton, NJ 08543,
West Lake International Symposium on Plasma Simulation; April, 2012 Influence of magnetic configuration on kinetic damping of the resistive wall.
Cyclic MHD Instabilities Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Seminar talk at the ‚Advanced Course‘ of EU PhD Network, Garching, September.
A. Kirk, 20th IAEA Fusion Energy Conference, Vilamoura, Portugal, 2004 The structure of ELMS and the distribution of transient power loads in MAST Presented.
Nonlinear Simulations of ELMs with NIMROD D.P. Brennan Massachussetts Institute of Technology Cambridge, MA S.E. Kruger Tech-X Corp, Boulder, CO A. Pankin,
Lecture Series in Energetic Particle Physics of Fusion Plasmas
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
Discrete Alfven Eigenmodes Shuang-hui Hu College of Sci, Guizhou Univ, Guiyang Liu Chen Dept of Phys & Astr, UC Irvine Supported by DOE and NSF.
Progress in Configuration Development for Compact Stellarator Reactors Long-Poe Ku Princeton Plasma Physics Laboratory Aries Project Meeting, June 16-17,
Physics Analysis for Equilibrium, Stability, and Divertors ARIES Power Plant Studies Charles Kessel, PPPL DOE Peer Review, UCSD August 17, 2000.
Non-disruptive MHD Dynamics in Inward-shifted LHD Configurations 1.Introduction 2.RMHD simulation 3.DNS of full 3D MHD 4. Summary MIURA, H., ICHIGUCHI,
RFA Experiments on the T2R RFP Open loop control experiments J.R. Drake 1), D. Gregoratto 2), T. Bolzonella 2), P.R. Brunsell 1), D. Yadikin 1), R. Paccagnella.
Computer simulations of fast frequency sweeping mode in JT-60U and fishbone instability Y. Todo (NIFS) Y. Shiozaki (Graduate Univ. Advanced Studies) K.
Massively Parallel Magnetohydrodynamics on the Cray XT3 Joshua Breslau and Jin Chen Princeton Plasma Physics Laboratory Cray XT3 Technical Workshop Nashville,
SIMULATION OF A HIGH-  DISRUPTION IN DIII-D SHOT #87009 S. E. Kruger and D. D. Schnack Science Applications International Corp. San Diego, CA USA.
Wave induced supersonic rotation in mirrors Abraham Fetterman and Nathaniel Fisch Princeton University.
6 th Japan-Korea Workshop on Theory and Simulation of Magnetic Fusion Plasmas Hyunsun Han, G. Park, Sumin Yi, and J.Y. Kim 3D MHD SIMULATIONS.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
JT-60U Resistive Wall Mode (RWM) Study on JT-60U Go Matsunaga 松永 剛 Japan Atomic Energy Agency, Naka, Japan JSPS-CAS Core University Program 2008 in ASIPP.
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
Overview of MHD and extended MHD simulations of fusion plasmas Guo-Yong Fu Princeton Plasma Physics Laboratory Princeton, New Jersey, USA Workshop on ITER.
Hybrid Simulations of Energetic Particle-driven Instabilities in Toroidal Plasmas Guo-Yong Fu In collaboration with J. Breslau, J. Chen, E. Fredrickson,
Numerical Simulation on Flow Generated Resistive Wall Mode Shaoyan Cui (1,2), Xiaogang Wang (1), Yue Liu (1), Bo Yu (2) 1.State Key Laboratory of Materials.
Boundaries, shocks, and discontinuities. How discontinuities form Often due to “wave steepening” Example in ordinary fluid: –V s 2 = dP/d  m –P/  
Rotation effects in MGI rapid shutdown simulations V.A. Izzo, P.B. Parks, D. Shiraki, N. Eidietis, E. Hollmann, N. Commaux TSD Workshop 2015 Princeton,
Point Source in 2D Jet: Radiation and refraction of sound waves through a 2D shear layer Model Gallery #16685 © 2014 COMSOL. All rights reserved.
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
Dynamics of ITG driven turbulence in the presence of a large spatial scale vortex flow Zheng-Xiong Wang, 1 J. Q. Li, 1 J. Q. Dong, 2 and Y. Kishimoto 1.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
NSTX APS DPP 2008 – RWM Stabilization in NSTX (Berkery)November 19, Resistive Wall Mode stabilization in NSTX may be explained by kinetic theory.
(National Institute for Fusion Science, Japan)
1) Disruption heat loading 2) Progress on time-dependent modeling C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD, 4/4/2011.
Electron inertial effects & particle acceleration at magnetic X-points Presented by K G McClements 1 Other contributors: A Thyagaraja 1, B Hamilton 2,
Stabilizing Shells in ARIES C. E. Kessel Princeton Plasma Physics Laboratory ARIES Project Meeting, 5/28-29/2008.
M. Onofri, F. Malara, P. Veltri Compressible magnetohydrodynamics simulations of the RFP with anisotropic thermal conductivity Dipartimento di Fisica,
Hybrid MHD-Gyrokinetic Simulations for Fusion Reseach G. Vlad, S. Briguglio, G. Fogaccia Associazione EURATOM-ENEA, Frascati, (Rome) Italy Introduction.
Contribution of KIT to LHD Topics from collaboration research on MHD phenomena in LHD S. Masamune, K.Y. Watanabe 1), S. Sakakibara 1), Y. Takemura, KIT.
Lecture Series in Energetic Particle Physics of Fusion Plasmas Guoyong Fu Princeton Plasma Physics Laboratory Princeton University Princeton, NJ 08543,
1 Lawrence Livermore National Laboratory Influence of Equilibrium Shear Flow on Peeling-Ballooning Instability and ELM Crash Pengwei Xi 1,2, Xueqiao Xu.
Kinetic MHD Simulation in Tokamaks H. Naitou, J.-N. Leboeuf †, H. Nagahara, T. Kobayashi, M. Yagi ‡, T. Matsumoto*, S. Tokuda* Joint Meeting of US-Japan.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
Effects of Flow on Radial Electric Fields Shaojie Wang Department of Physics, Fudan University Institute of Plasma Physics, Chinese Academy of Sciences.
Influence of pressure-gradient and average- shear on ballooning stability semi-analytic expression for ballooning growth rate S.R.Hudson 1, C.C.Hegna 2,
1 A Proposal for a SWIM Slow-MHD 3D Coupled Calculation of the Sawtooth Cycle in the Presence of Energetic Particles Josh Breslau Guo-Yong Fu S. C. Jardin.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
Chernoshtanov I.S., Tsidulko Yu.A.
NIMROD Simulations of a DIII-D Plasma Disruption
Simulations of NBI-driven Global Alfven Eigenmodes in NSTX E. V. Belova, N. N. Gorelenkov, C. Z. Cheng (PPPL) NSTX Results Forum, PPPL July 2006 Motivation:
Numerical Study on Ideal MHD Stability and RWM in Tokamaks Speaker: Yue Liu Dalian University of Technology, China Co-Authors: Li Li, Xinyang Xu, Chao.
Relativistic MHD Simulations of jets Relativistic MHD Simulations of jets Abstract We have performed 3D RMHD simulations to investigate the stability and.
Neoclassical Effects in the Theory of Magnetic Islands: Neoclassical Tearing Modes and more A. Smolyakov* University of Saskatchewan, Saskatoon, Canada,
Simulations of Energetic Particle Modes In Spherical Torus G.Y. Fu, J. Breslau, J. Chen, E. Fredrickson, S. Jardin, W. Park Princeton Plasma Physics Laboratory.
Nonlinear Simulations of Energetic Particle-driven Modes in Tokamaks Guoyong Fu Princeton Plasma Physics Laboratory Princeton, NJ, USA In collaboration.
Interaction between vortex flow and microturbulence Zheng-Xiong Wang (王正汹) Dalian University of Technology, Dalian, China West Lake International Symposium.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Unstructured Meshing Tools for Fusion Plasma Simulations
Mechanisms for losses during Edge Localised modes (ELMs)
Huishan Cai, Jintao Cao, Ding Li
Finite difference code for 3D edge modelling
Influence of energetic ions on neoclassical tearing modes
Stabilization of m/n=1/1 fishbone by ECRH
Presentation transcript:

Halo Current and Resistive Wall Simulations of ITER H.R. Strauss 1, Linjin Zheng 2, M. Kotschenreuther 2, W.Park 3, S. Jardin 3, J. Breslau 3, A.Pletzer 3, R. Paccagnella 4, L. Sugiyama 5, M. Chu 6, M. Chance 6, A. Turnbull 6 1)New York University, New York, New York,USA 2)Institute for Fusion Studies, University of Texas, Austin, Texas 78712, USA 3)Princeton University Plasma Physics Laboratory, Princeton, New Jersey,USA 4)Instituto Gas Ionizzati del C.N.R., Padua, Italy 5)MIT, Cambridge, MA,USA 6)General Atomics, P.O. Box 85608, San Diego, CA 92186, USA

Outline Resistive boundary in simulational problems Halo current – M3D : nonlinear, resistive MHD –VDE –Disruption –RWM (resistive wall mode) RWM – AEGIS : linear ideal MHD, resistive wall –Stabilization by rotation, Alfven resonance –Thick wall effect

Halo Current Halo current: –current flowing on open field lines into wall Causes stress on walls –Toroidal asymmetry: TPF (toroidal peaking factor) –Halo current fraction –Want to confirm ITER database with simulation Occurs during: –VDE (vertical displacement event) –Major disruption –External kink / (RWM) Resistive wall mode

Plasma regions Core separatrix halo 1st wall Outer wall Outer vacuum plasma – halo – vacuum model core halo Resistive MHD with self consistent resistivity – proportional to temperature to -3/2 power Parallel thermal conduction –Separatrix thermally isolates hot core from cold halo –In 3D disruptions, stochastic magnetic field quenches core temperature, raising resistivity and quenching current Outer vacuum –Green’s function method (GRIN) –Thin wall approximation –Continuity of normal magnetic field component –Calculate jump of tangential components, electric field

VDE Instability 2D instability Growth rate proportional to wall resistivity Halo current flows when core near wall Poloidal flux function

Toroidal peaking factor and halo current fraction Normal component of poloidal Current flowing out through the boundary as function of toroidal angle Toroidal peaking factor Halo current fraction of Toroidal current Inverse relation of TPF to Halo current fraction

3D disruptions TPF: Toroidal Peaking Factor - toroidal asymmetry of ITER halo currents Halo Current Fraction – measure of halo current Disruption can combine with VDE – increasing its growth rate Case of internal kink with large q=1 radius Halo current flows along contours of RB t intersecting the wall Poloidal flux(VDE) temperature RB t

toroidal peaking factor and halo current fraction current temperature Toroidal Peaking factor Halo/total current x 10 TPF = 2, F h = 0.35 Temperature and current vs. time TPF and F h vs. time

Nonlinear RW – external kink TPF = 1.1, F h =.2 Perturbed Poloidal fluxtemperature ITER AT: m/n = 3/1 RB t

Results are consistent with ITER database x o X – kink instability O – resistive wall mode TPF FhFh

Scaling of RWRP mode Simulation of RWM is complicated by plasma resistivity Finn, 1995, Betti 1998 RWM interacts with tearing/electromagnetic resistive ballooning mode

New MHD code: AEGIS A daptive E i G enfunction I ndependent S olution Features Radial Adaptive mesh to resolve Alfven resonances Small matrix size formulation: AEGIS: M, GATO or PEST: M x N (sparse) M: no. of poloidal components, N: radial grids Applicable both for low and high n modes Benchmark with GATO: good agreement in beta limit, growth rate, critical wall position, and mode shape

Benchmark with GATO Good agreement in all aspects: beta limit, growth rate, critical wall position, and mode shape… AEGISGATO

Rotation effect on RWMs Previous results: Rotation stabilization results from sound wave resonance or generally particle wave resonance Current results: Shear Alfven continuum damping can effectively stabilize RWMs. --- this fine singular layer effect can be resolved by AEGIS due to its adaptive feature.

Parameters: q(0) = 1.05, q(95) = 3 volume average beta= 0.062, beta_n = no wall limit beta_n = 3.4 Eigenmode: Alfven resonances at q = 2, 3, 4 Resonances are singular in limit of zero growth rate Grid adapts to resolve resonances

Low Mach number rotation stabilization for ITER configuration Marginal wall position vs. rotation frequency RWM growth rate vs. wall position for different rotation frequencies Growth rate drops sharply at stability boundary Stability window in wall position for nonzero rotation

Wall thickness effect on RWMs Motivation: ITER wall is 0.45 thick. Method: Adaptive shooting of the Euler-Lagrange equation in the wall region. Results: The part of the wall located beyond the ideal-wall critical position gives no contribution for stability. Thick wall slows growth. Effects of rotation and thick wall to be studied later.

Effect of wall thickness on growth rate Dashed curve represents the thin- wall-theory estimate and b is the wall position Growth rate vs wall position with different wall thickness Thick wall has no effect outside the critical wall position For less than critical wall position, thickness slows mode

Summary Halo current calculated in nonlinear M3D simulations Model simulates VDE, disruption, thermal & current quench TPF and F h consistent with ITER database Resistive plasma modifies RWM scaling AEGIS RWM simulations of rotation stabilization with self consistent Alfven damping, no model parameters Thick wall slows RWM growth rate, but has no effect outside critical wall position

Phase change across to the resonance Singular layer equation d/dx (x^2- Ω^2) d  /dx =0 Solution:  = (b /2 Ω) l n (x- Ω )/(x+ Ω ) +a At -  :  = a - b/x At +  :  = a - b/x + i b  / Ω Integration orbit: Ω = Ω_rot + i  + 