Supported by. The drift kinetic and rotational effects on determining and predicting the macroscopic MHD instability

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

Supported by. Validation of a new fast ion transport model for TRANSP. M. Podestà - PPPL

Supported by. Relation of pedestal stability regime to the behavior of ELM heat flux footprints in NSTX-U and DIII-D. J-W. Ahn 1

Supported by. The dependence of H-mode energy confinement and transport on collisionality in NSTX

Supported by. Suppression of TAE and GAE with HHFW heating

Investigations of pedestal turbulence and ELM bursts in NSTX H-mode plasmas

D. Smith, R. Fonck, G. McKee, D. Thompson, and I. Uzun-Kaymak

M. Podestà, M. Gorelenkova, D. S. Darrow, E. D. Fredrickson, S. P. Gerhardt, W. W. Heidbrink, R. B. White and the NSTX-U Research Team

NSTX. Electron gyro-scale fluctuations in NSTX plasmas. David Smith, PPPL. Supported by

David R. Smith UW-Madison

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

Alfvén Cascade modes at high β in NSTX*

RWM Control Code Maturity

UCLA POSTECH UCSD ASIPP U

Dynamic retention and deposition in NSTX measured with quartz microbalances

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

NSTX Results and Plans toward 10-MA CTF

Modelling Toroidal Rotation Damping in ITER Due to External 3D Fields

Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas

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

Resistive Wall Mode Control in DIII-D

Advances in Global MHD Mode Stabilization Research on NSTX

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta

Theory for Neoclassical Toroidal Plasma Viscosity in a Toroidally Symmetric Torus. K. C. Shaing

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

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

Plasma Stability in Tokamaks and Stellarators

DIII D. by F. Turco 1. New York, January 23 rd, 2015

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

ELM control with RMP: plasma response models and the role of edge peeling response

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

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

Energetic particle modes: from bump on tail to tokamak plasmas

TURBULENT TRANSPORT THEORY

Performance limits. Ben Dudson. 24 th February Department of Physics, University of York, Heslington, York YO10 5DD, UK

Nonlinear MHD effects on TAE evolution and TAE bursts

Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD

MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

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

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

Nonlinear Simulation of Energetic Particle Modes in JT-60U

Nonlinear Consequences of Weakly Driven Energetic Particle Instabilities

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

RWM Control in FIRE and ITER

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

Macroscopic Stability of High β N MAST Plasmas

MHD Linear Stability Analysis Using a Full Wave Code

Z. Lin University of California, Irvine, CA 92697, USA. Supported by SciDAC GPS-TTBP, GSEP & CPES

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

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

Damping and drive of low frequency modes in tokamak plasmas

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

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

MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling

The Effect of Energetic Particles on Resistive Wall Mode Stability in MAST

Effects of Noise in Time Dependent RWM Feedback Simulations

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

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

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

Control of Neo-classical tearing mode (NTM) in advanced scenarios

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions

Advanced Tokamak Research in JT-60U and JT-60SA

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

Global gyrokinetic modeling of geodesic acoustic modes and shear Alfvén instabilities in ASDEX Upgrade.

Chalmers Publication Library

Effects of Alpha Particle Transport Driven by Alfvénic Instabilities on Proposed Burning Plasma Scenarios on ITER

Rotation and Neoclassical Ripple Transport in ITER

Requirements for Active Resistive Wall Mode (RWM) Feedback Control

A.G. PEETERS UNIVERSITY OF BAYREUTH

Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry

GTC Simulation of Turbulence and Transport in Tokamak Plasmas

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod

Modeling of ELM Dynamics for ITER

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

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

Energetic Particle Physics in Tokamak Burning Plasmas

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

Hybrid Kinetic-MHD simulations with NIMROD

MHD. Jeff Freidberg MIT

Effects of drag and diffusion on nonlinear behavior of EP-driven instabilities.

Nonlinear Energetic Particle Transport in the Presence of Multiple Alfvénic Waves in ITER

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

Microturbulence in optimised stellarators

Gyrokinetic Microtearing Studies

Flow and dynamo measurements in the HIST double pulsing CHI experiment

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges

Modelling of Frequency Sweeping with the HAGIS code

Hybrid Kinetic-MHD simulations with NIMROD

What we ve learned so far about the Stability of Plasma Confined by a Laboratory Dipole Magnet

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

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Comparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR

Alpha Particle Transport Induced by Alfvénic Instabilities in Proposed Burning Plasma Scenarios

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Edge Zonal Flows and Blob Propagation in Alcator C-Mod P5.073 EPS 2011

Current-driven instabilities

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas

Gyrokinetic Simulations of Tearing Instability

Effects of fast ion phase space modifications by instabilities on fast ion modeling

Transcription:

NSTX-U Supported by The drift kinetic and rotational effects on determining and predicting the macroscopic MHD instability Coll of Wm & Mary Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Lehigh U Nova Photonics ORNL PPPL Princeton U Purdue U SNL Think Tank, Inc. UC Davis UC Irvine UCLA UCSD U Colorado U Illinois U Maryland U Rochester U Tennessee U Tulsa U Washington U Wisconsin X Science LLC Z.R. Wang 1, J. E. Menard 1, Y.Q. Liu 2, J.-K. Park 1 1 Princeton Plasma Physics Laboratory 2 Culham Centre for Fusion Energy, Culham Science Centre Integrated Simulations Workshop May 18, 2015 Culham Sci Ctr York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAEA Inst for Nucl Res, Kiev Ioffe Inst TRINITI Chonbuk Natl U NFRI KAIST POSTECH Seoul Natl U ASIPP CIEMAT FOM Inst DIFFER ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching ASCR, Czech Rep

Background Kinetic effects on resistive wall mode, ideal wall mode, plasma response etc. have been extensively studied since fluid MHD approach fails to accurately treat these problems. MARS-K code has been largely upgraded to improve numerical stability and include more kinetic physics e.g. finite orbit width effect and energy dependence of collisionality. Successful benchmark has been carried out among MARS-K, IPEC-PENT, MISK and HAGIS for calculation of kinetic effects. Proposed Research for Reliable Prediction of MHD Instability Explore MHD macroscopic instability through Nyquist contour technique in experiments and compare with numerical simulation. Tearing Instability and NTV Torque in presence of external fields. Further improve kinetic model to include perturbed E and experimental energetic particles distribution function. Study kinetic effects in non-linear MHD simulation. 2

Outline Hybrid kinetic-mhd modelling using MARS-K Progress of applying MARS-K to determine and predict MHD instability Kinetic effects on resistive wall mode instability in ITER Kinetic and rotational effects on ideal wall mode instability in NSTX Quantitative validation of hybrid kinetic-mhd theory with DIII-D n=1 plasma response experiment Anticipated MARS application to compare with experiments Summary and future plan of MARS code development 3

Drift-kinetic equation: df L 1 MARS-K: Hybrid Drift-Kinetic MHD Formulation MARS-K solves linearized MHD equations with perturbed kinetic pressure, including toroidal flow V f =RW, vacuum, resistive wall and external coils. MHD equations: i ω + nω ξ = v + Inertial term ξ Ω R 2 ϕ iρ ω + nω v = p + j B 0 + J 0 b + ρ 2ΩZ v v Ω R 2 ϕ ρξ ΩZ V 0 i ω + nω b = v B 0 + b Ω R 2 ϕ (ηj) Resistivity i ω + nω p = v P 0 ΓP 0 v Mode eigenvalue j = b dt = f ε 0 H1 t f 0 H1 P φ φ ν 1 efff L H 1 : perturbed Lagrangian replaced by kinetic pressure MARS-K in self-consistent approach: Drift kinetic effects can modify mode eigenfunction. Coriolis force Kinetic pressure p and p couple with MHD equations Resonant operator in f L 1 : Precession drift p = pi + p bb + p Diamagnetic drift I bb p e iωt+inφ = dγmv 2 f L 1 e,i p e iωt+inφ = dγ 1 2 Mv 2 f L 1 e,i Centrifugal force Mode eigenvalue n ω N + εk 3/2 ω T + ω E ω λ ml = nω d + α m + nq + l ω b + nω E ω iν eff Bounce/Transit EXB Crook Collisions Y.Q. Liu et al, PoP 2014 NSTX-U 4

MARS-K: First Order Finite Orbit Width (FOW) Correction: Important For Energetic Particles (EPs) Solution of the drift kinetic equation for the perturbed distribution function perturbed kinetic pressures (non-adiabatic part) poloidal Fourier harmonics zero-order term first-order FOW correction terms 2 nd & 3 rd terms come from FOW correction to equilibrium distribution function 4 th term comes from FOW correction to perturbations 2 nd term disappears for trapped particles [Liu et al., PoP 21, 056105 (2014)] 5

Outline Hybrid kinetic-mhd modelling using MARS-K Progress of applying MARS-K to determine and predict MHD instability Kinetic effects on resistive wall mode instability in ITER Kinetic and rotational effects on ideal wall mode instability in NSTX Quantitative validation of hybrid kinetic-mhd theory with DIII-D n=1 plasma response experiment Anticipated MARS application to compare with experiments Summary and future plan of MARS-K development 6

ITER 9MA: Self-Consistent Computations of Hybrid Kinetic MHD: Isotropic Slowing Down Model (Fusion Born a s) Fluid model, w/o plasma flow, predicts unstable RWM between no-wall & ideal-wall beta limits Fluid theory [Liu et al., PoP 21, 056105 (2014)] 7

ITER 9MA: Self-Consistent Computations of Hybrid Kinetic MHD: Isotropic Slowing Down Model (Fusion Born a s) Kinetic theory, including precessional drift resonance contributions from both thermal & energetic particles, predicts marginal stability for ITER target plasma Fluid theory Precession resonance [Liu et al., PoP 21, 056105 (2014)] 8

ITER 9MA: Self-Consistent Computations of Hybrid Kinetic MHD: Isotropic Slowing Down Model (Fusion Born a s) Adding bounce & transit resonance contributions (ZOW), from both thermal & energetic ions, further stabilize the mode Fluid theory Precession resonance All resonances w/ ZOW [Liu et al., PoP 21, 056105 (2014)] 9

ITER 9MA: Self-Consistent Computations of Hybrid Kinetic MHD: Isotropic Slowing Down Model (Fusion Born a s) Further adding 1 st order FOW correction, to bounce & transit resonance contributions of EPs, stabilises the mode at high beta but destabilises the mode at lower beta Kinetic effects significantly reduce growth rates of the RWM Fluid theory Precession resonance All resonances w/ ZOW All resonances w/ FOW [Liu et al., PoP 21, 056105 (2014)] 10

NSTX: Experimental b N Limit of n=1 Ideal Wall Mode Can Be Predicated by Hybird Kinetic-MHD Calculation Experimental fluid rotation destabilizes plasma and leads to under predication of b N limit in fluid MHD calculation. Kinetic effects stabilize ideal wall mode and agree with experimental b N and mode frequency. NSTX shot 119621, t=610ms Fluid b N limit~5.6 for low Wt A =3% Fluid b N limit~4.2 for experimental W(0)t A =20% b N range Kinetic b N limit~5.3-5.5 for expt. W(0)t A =20% Menard, Wang and Liu et al., PRL 113, 255002 (2014)] 11

NSTX:Eigenfunction of Ideal Wall Mode is Modified by Kinetic Effects and Plasma Rotation The eigenfunctions of radial plasma displacement solved by ideal MHD and hybrid kinetic MHD are compared. The eigenfunctions are modifed in both core and edge by kinetic effects and plasma rotation. Soild: Fluid IWM W(0)t A =0, Dashed: Kinetic IWM W(0)t A =20% Kinetic IWM m=2 m=1 Fluid IWM m=3 m=4 12

DIII-D: n=1 Plasma Response Predicted by Kinetic-MHD Agrees with Internal Structure Measurement from Soft X-Ray n=1 Internal response structure comparison Simulated 2D radial displacement Fluid response 1 12 SXR sightline geometry Exp Kinetic response The quantitative agreement between experiment and kinetic plasma response shows validation of hybrid kinetic MHD theory (MARS-K). Wang, Lanctot, Liu et al., PRL 114, 145005(2015) 13

Outline Hybrid kinetic-mhd modelling using MARS-K Progress of applying MARS-K to determine and predict MHD instability Kinetic effects on resistive wall mode instability in ITER Kinetic and rotational effects on ideal wall mode instability in NSTX Quantitative validation of hybrid kinetic-mhd theory with DIII-D n=1 plasma response experiment Anticipated MARS application to compare with experiments Summary and future plan of MARS-K development 14

Nyquist Contour Significantly Improve Physical Understanding of MHD instability and Plasma Response Nyquist contour can be formed by scanning coil frequency from -infinity to +infinity. Fluid vs. Kinetic cases shows different Nyquist contours. Comparing experimental and simulated Nyquist contour can. Further validate hybrid kinetic-mhd theory; Reveal multi-mode plasma response to n=1 and n=2 perturbation; infer growth/damping rate of (multiple) mode(s) (Padé approximation); MARS simulation of DIII-D n=1 Nyquist contour MARS Nyquist Fluid w/o Rotation Fluid + Rotation Kinetic w/o Rotation Kinetic + Rotation Padé approximation 1 st mode g 1 = 79.23 (a.u.) 2 nd mode g 2 = - 14.14 (a.u.) 3 rd mode g 3 = - 85.16(a.u.) 15

Summary Kinetic effects with FOW significantly reduce growth rate of RWM in ITER. Strong rotation and kinetic effects substantially modify the ideal-wall limit in ST plasmas with high b. Kinetic IWM calculation reproduce experimental ideal wall b limit and mode frequency that fluid calculations cannot. Validation of hybrid kinetic-mhd theory with DIII-D experiments indicates importance of kinetic modification on response(mode) structure. Future Plan Application of MARS-K to study experimental Nyquist contour and tearing instability Inclusion of the perturbed electrostatic potential in hybrid formulation Implement the experimental EPs distribution function Study kinetic effects in non-linear MHD simulation. Possibility to do real time feedback control with hybrid kinetic-mhd? 16

Numerical Study for ITER 9MA Steady State Scenario (340MW and Q=5) ITER target: b N =2.94 Peq safety factor q min =1.58 W 0 =6kHz =2.7%w A P a /P th ~20% 17

Adding perturbed electrostatic potential (work in progress) Perturbed electrostatic potential and quasi-neutrality f f a df dt L L f P a f E Ze A c Mv (0) f f P L L t 2 (0) R Zef κ ξ Zef f P (0) f E (0) L B B B (0) f ( B B ) Ze( ) (0) ξ f ξ f ( f f ) Z j j, a j, L dv j 0 18

MARS Has Numerical Capability to Study Tearing Instability and NTV Torque in Presence of External Fields MARS-Q can do physical analysis in terms of the small island in the quasi-linear approach. The code can be used to simulate dynamics of tearing mode in the experiments. Plasma rotational effect can be included. The code includes the JxB resonant torque + Neoclassical toroidal viscosity(ntv) torque MAST plasma with n=3 magnetic perturbation Time evolution of (2,1) island width Rotation damping Y.Q. Liu et al, PPCF 2012 G.Z. Hao et al, PoP 2014 MARS-Q will be validated with NSTX-U experiments for tearing instability study. 19

Amplitude(Gauss/KA) DIII-D: Plasma Response Predicted by Kinetic-MHD Agrees with Internal Structure Measurement from Soft X-Ray Comparison of n=1 plasma response on ISL magnetic sensor Internal response structure comparison 2D radial displacement Fluid plasma response 1 12 SXR sightline geometry Exp Kinetic plasma response Wang, Lanctot, Liu et al., PRL to be published (2015) The quantitative agreement between experiment and kinetic plasma response shows validation of hybrid kinetic MHD theory. 20