Self-consistent full wave simulations of lower hybrid waves

Similar documents
Challenges in self-consistent full wave simulations of lower hybrid waves

Full wave simulations of lower hybrid wave propagation in tokamaks

Full wave simulations of lower hybrid wave propagation in tokamaks

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

Time Dependent evolution of RF-generated non-thermal particle distributions in fusion plasmas

Full-wave Electromagnetic Field Simulations in the Lower Hybrid Range of Frequencies

Integration of Fokker Planck calculation in full wave FEM simulation of LH waves

Development of LH wave fullwave simulation based on FEM

Nonthermal Particle and Full-wave Effects on Heating and Current Drive in the ICRF and LHRF Regimes

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

Full-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak

TH/P6-08. CompX, Del Mar, CA 92014, USA; 2Xcel Engineering, Oak Ridge, TN 37830, USA; 3PSFC-MIT,Cambridge, MA 02139

Analysis of Ion Cyclotron Heating Issues for ITER

Full wave simulations of lower hybrid waves in toroidal geometry with Non-Maxwelian electrons

Time-domain simulation and benchmark of LHCD experiment at ITER relevant parameters

ICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation

Modelling of the EAST lower-hybrid current drive experiment using GENRAY/CQL3D and TORLH/CQL3D

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

Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS

Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas

Theory Work in Support of C-Mod

Recent results from lower hybrid current drive experiments on Alcator C-Mod

1 THW/P7-09 Comparison of Quasi-linear and Exact Ion Cyclotron Resonant Heating Diffusion, With and Without Finite Width Ion Orbits Abstract.

SciDAC CENTER FOR SIMULATION OF WAVE-PLASMA INTERACTIONS

Status of RF Modeling in Integrated Simulations

Paraxial WKB method applied to the lower hybrid wave propagation a)

AST 553. Plasma Waves and Instabilities. Course Outline. (Dated: December 4, 2018)

Full Wave Simulations of Fast Wave Mode Conversion and Lower Hybrid Wave Propagation in Tokamaks

Measurement of lower hybrid waves using microwave scattering technique in Alcator C-Mod

Absorption of lower hybrid waves in the scrape off layer of a diverted tokamak

GA A24016 PHYSICS OF OFF-AXIS ELECTRON CYCLOTRON CURRENT DRIVE

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D

Theory and Simulation Support for Alcator C-Mod

Theory and Modeling Support for Alcator C-Mod

Theory and Modeling Support for Alcator C-Mod

On Electron-Cyclotron Waves in Relativistic Non-Thermal Tokamak Plasmas

Explanation of prompt growth of ECE signal in tokamak runaway electron experiments

GA A23698 ELECTRON CYCLOTRON WAVE EXPERIMENTS ON DIII D

Lower Hybrid RF: Results, Goals and Plans. J.R. Wilson Alcator C-Mod Program Advisory Meeting January 27, 2010

Review of recent experimental and modeling advances in the understanding of lower hybrid current drive in ITER-relevant regimes

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

Improvements to wave codes

RELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE

DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING

EXC/P2-02. Experiments and Simulations of ITER-like Plasmas in Alcator C-Mod

Integrated modeling of LHCD non- induc6ve scenario development on Alcator C- Mod

SPECTRUM AND PROPAGATION OF LOWER HYBRID WAVES IN THE ALCATOR C TOKAMAK

Theory and Modeling Support for Alcator C-Mod

Observation of Co- and Counter Rotation Produced by Lower Hybrid Waves in Alcator C-Mod*

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

TURBULENT TRANSPORT THEORY

Progress on Quantitative Modeling of rf Sheaths

Review of Recent Experimental and Modeling Progress in the Lower Hybrid Range of Frequencies at ITER Relevant Parameters

Benchmarking of electron cyclotron heating and current drive codes on ITER scenarios within the European Integrated Tokamak Modelling framework

Electron Cyclotron Emission Simulation from TCABR Plasmas

Overview of Alcator C-Mod Research

GA A22141 ELECTRON CYCLOTRON HEATING AND CURRENT DRIVE IN ITER

The fast-ion distribution function

Hard Xray Diagnostic for Lower Hybrid Current Drive on Alcator C- Mod

ITB Transport Studies in Alcator C-Mod. Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co

Heating and Current Drive by Electron Cyclotron Waves in JT-60U

Theory and Modeling Support for Alcator C-Mod

Lower Hybrid Wave Induced Rotation on Alcator C-Mod* Ron Parker, Yuri Podpaly, John Rice, Andréa Schmidt

Propagation of Radio Frequency Waves Through Fluctuations in Plasmas

ICRF Mode Conversion Flow Drive on the Alcator C Mod Tokamak

Integrated Full Wave Analysis of RF Heating and Current Drive in Toroidal Plasmas

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center

A Study of Directly Launched Ion Bernstein Waves in a Tokamak

Fast Ion Measurement in the Alcator C-Mod plasma: How, Why, and Who Cares*

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

Observation of fishbone-like internal kink modes during LHCD operation in Alcator C-Mod

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus)

Ray-tracing and Fokker Planck modelling of the effect of plasma current on the propagation and absorption of lower hybrid waves

GA A23066 ENHANCEMENT OF RUNAWAY AVALANCHE BY LOWER HYBRID WAVES

plasm-ph/ Feb 1995

September Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts USA

The Plasma Phase. Chapter 1. An experiment - measure and understand transport processes in a plasma. Chapter 2. An introduction to plasma physics

JP Sta,onary Density Profiles in Alcator C Mod

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

Fast ion generation with novel three-ion radiofrequency heating scenarios:

Heating and current drive: Radio Frequency

C-Mod Transport Program

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

Finite-Orbit-Width Effect and the Radial Electric Field in Neoclassical Transport Phenomena

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

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

Production and Damping of Runaway Electrons in a Tokamak

Scattering of ECRF waves by edge density fluctuations and blobs

Ray Tracing and Full-wave Simulation of KSTAR LH Wave

Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D

Combined LH and ECH Experiments in the FTU Tokamak

Observations of Rotation Reversal and Fluctuation Hysteresis in Alcator C-Mod Plasmas

Predictive Study on High Performance Modes of Operation in HL-2A 1

Active and Passive MHD Spectroscopy on Alcator C-Mod

Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod

PSFC/JA D.R. Ernst, N. Basse, W. Dorland 1, C.L. Fiore, L. Lin, A. Long 2, M. Porkolab, K. Zeller, K. Zhurovich. June 2006

Simulation of alpha particle current drive and heating in spherical tokamaks

Space Plasma Physics Thomas Wiegelmann, 2012

Transcription:

18 th RF Topical Conference Gent, June 2009 Self-consistent full wave simulations of lower hybrid waves John C. Wright P. T. Bonoli - MIT E.J. Valeo, C. K. Phillips - PPPL R. W. Harvey - Comp-X with thanks to A. Schmidt, G. Wallace, R. Parker, M. Porkolab M. Brambilla

Participants in the Center for Simulation of Wave-Plasma Interactions L.A. Berry, D.B. Batchelor, E.F. Jaeger, E. D`Azevedo D. Green D. Smithe P.T. Bonoli, J.C. Wright H. Kohno, A.S. Richardson C.K. Phillips, E. Valeo N. Gorelenkov, H. Qin R.W. Harvey, A.P. Smirnov N.M. Ershov M. Brambilla R. Bilato M. Choi R. Maggiora D. Milanesio D. D Ippolito, J. Myra 2

Outline Introduction to Lower Hybrid waves Modeling LH waves Ray tracing Full Wave Comparisons between approaches Full wave effects, non-thermal electrons, relativistic effects Summary and Conclusions 3

Motivation Predicted HXR Spectra Agree Well with Measured Spectra Except Narrower [Bonoli PoP2008] Assess full wave effects the computational resources needed to do this now exist. Electric field is needed for Count Rate (s -1 kev -1 ) Direct evaluation of the Kennel- Engelmann quasilinear accounting for phase interference, diffusion sheath interactions, 8 coupling to Newtonian and Monte- 6 Carlo calculations of plasma response 4 (diffusion, distribution fn evolution). 2 Implementation of boundary conditions is well defined. 0 x 10 4 16 14 12 10 Measured and Simulated HXR Spectra Experiment Simulation - CQL3D 24 kev 34 kev 44 kev 5 10 15 20 25 30 Channel # 4

Conductivity Relation - LHRF Regime LHCD Regime: Ω 2 ci ω2 Ω 2 ce and ω 2ω LH Unmagnetized ions Strongly magnetized electrons [(k ρ e ) 2 1] Wave equation is sixth order with two propagating modes, one damped: Mode converted ion plasma wave is not propagative, so drop sixth order term Electrostatic LH slow wave branch Electromagnetic LH fast wave branch Wave lengths are very short: Index of refraction Predicts an accessibility criterion: Density Bonoli PoF 1982

LH Absorption physics=>weak damping characterizes present tokomaks Parallel refractive indexes are geometrically up-shifted as waves propagate to smaller major radius. Poloidal asymmetries can cause spread in m spectrum. Quasilinear damping occurs at ω/k v te ~3 => Poloidal broadening so lower temperatures require higher n for damping. Higher parallel refractive indexes are more accessible to the interior of the plasma but also damp at lower temperatures=larger minor radii. ~1.4 in C-Mod Current drive scales as 1/n e n 2 and n acc [n e,b] sets minimum n => operation in weak damping regime for T e0 <16keV 6

Approaches to solution WKB expansions: ray tracing (GENRAY, ACCOME) and beam tracing (LHBEAM) are asymptotic approximations to the wave equation, k required. => can be problems with boundaries Full Wave(TORIC-LH): solves Maxwell's equations directly, yields the electric field. 7

TORIC Full Wave Code TORIC [Brambilla 1999] was developed with an FLR model for the plasma current response, J P, for ion cyclotron waves and recently extended with an asymptotic form for lower hybrid waves. The antenna is modeled as a current sheet, J A for ICRF and as the mouth of a wave guide with imposed E for LH. It solves Maxwell's equations for a fixed frequency (Helmholtz problem) assuming toroidal symmetry in a mixed spectral-finite element basis. This is the physical optics solution. 8

Simulation model is a coupled full wave and Fokker-Planck system CQL3D (Harvey 1992IAEA) TORIC-LH (Wright 2004CPC,2009PoP) Bounce averaged Fokker-Planck code that solves for new distribution function from RF quasilinear flux, provides f(v) f e v Dielectric for LH uses zero FLR electrons and unmagnetized ions. Calculates the RF fields and the quasilinear flux. => f e (v) and E(x) are self-consistent Simulations use EFIT reconstructed magnetic equilibria. Electron distribution functions from iteration with a Fokker-Planck code are used for dielectric. 9

Lower Hybrid Wave Equation The pressure driven term σ is responsible for the ion plasma LH branch. In regimes of experimental interest it is nearly vanishing. We drop this term and solve only for the fast and slow LH waves. The dielectric assumes zero FLR electrons and unmagnetized ions (thermal damping in P retained). This reduced system is much less stiff and faster to solve. Electron FLR terms discovered to cause SCK like numerical instability [Swanson PF 1981], because k in S,D, and σ must be consistent. Can drop because of negligible size. 10

Removal of small FLR e - terms yields stable solution Strong absorption n =3.6 Weak absorption n =1.55 E E After zeroing out FLR electron terms fields from the antenna into the plasma are apparent. Interference is significant in low n case.

Full wave code approaches Alcator C. 10 6 mesh pts. n =-2.5, B 0 =8T, n e0 =5x10 19 m -3,T e0 =5keV. TORIC-LH See B58 Shiraiwa and also B56 Peysson A42 Van Eester COMSOL-LH Shiraiwa, Meneghini, Parker AORSA Jaeger COMSOL with 2D FE TORIC-LH with 1D FE/1D Spectral AORSA with 2D spectral Each approach as advantages and difficulties: CPU-hrs: COMSOL-LH 13, TORICLH 80, AORSA 32k (ray tracing ~ minutes) but wall clock times for all three are comparable given number of processors used. (2hrs) COMSOL: 2D elements can model wall and separatrix region; sparse matrix scales well The plasma dielectric: Alcator C-Mod. 512x512. n =-4.0, B 0 =2T, n e0 =6x10 19 m -3,T e0 =4keV. COMSOL-LH requires real space dielectric formulation, doesn't have algebraic k TORIC-LH needs care in treating FLR truncation AORSA All Orders treatment most general, can handle fast ion interactions

Single pass is well converged with linear damping (Maxwellian) Single pass damping on a Maxwellian plasma is converged. Little interference is evident. Power is very localized in single pass. <- Spectrum is converged at 1023 modes r/a n = -2.55, ne0=7e19 m -3 Te0 = 10 kev, B0=4T

Comparison with ray tracing in weak damping limit Maxwellian damping in both cases. Good agreement in power deposition locations. Alcator C-Mod. n =-1.55, B 0 =5.3T, n e0 =7x10 19 m -3,T e0 =2.3keV. But,field amplitudes are magnified by cavity effect [Q~ω/γ~200]

Weak damping requires quasilinear f e (v) for self-consistent treatment Bulk damping Accessibility cutoff Width indicates poloidal broadening of Δn /n 0 ~ Δm/q n φ r/a The poloidal power spectrum shows lack of convergence at outer flux surfaces, Also magnification of unit amplitude applied field.

<D ql > bounce for FP coupling v 0 /v te v 0 /v te <Dql> v 0 /v te <Dql> Calculated following full wave treatment in Wright NF1997. Bounce averaged, Larmor cutoff [ J 0 (k ρ i ) ] at high perpendicular energies. Nonrelativistic. Note the symmetry in the trapped region. D ql ~ Σu 4 E (m1) E *(m2) e iθ(m1-m2) δ(ω-k (m1) v ) γ 2 v Φ (m1) v Φ (m2) u =γv, γ=1 v 0 /v te

Effect of non Maxwellian damping Step0 Step1 Step2 Convergence achieved in two iterations. Note the reduction in peak amplitude. Fields are less space filling now.

Effect of non Maxwellian damping r/a Energy in poloidal modes plotted for selected flux surfaces. Spectrum is converged. Power is a bit broader. Power density and Poynting flux. Power is normalized to the total power.

Example of QL tail formation, HXR spectrum from TORICLH/CQL3D TORIC results X 4 Compared to experiment Broad plateau formation observed. Pitch angle scattering creates high energy tails ~> 500 kev Synthetic HXR from CQL3D/TORICLH is narrower and weaker than experimental measurement =>What effects are missing?

Future Research More physics in calculation of D ql Inclusion of 3-D non-linear effects through multiple toroidal modes of antenna. Relativistic effects. Non-linear broadband effect in Dql => study with Newtonian Dql evaluation, e.g. Harvey this meeting with ions. Study the relative role of poloidal mode coupling (nonconstancy of m) versus diffraction in observed spectral broadening. Application: synthetic PCI for LH on Alcator C-Mod (requires electric fields): 20

Relativistic effects on Dql Allowing for relativistic effects, γ>1, u v. D ql ~ Σu 4 E (m1) E *(m2) e iθ(m1-m2) δ(ω-k (m1) v ) γ 2 v Φ (m1) v Φ (m2) Main effect is transformation of the resonance condition, which depends only on electron velocity, not momentum. Becomes hyperbolic. ω=k v ω=k u /γ = (n 2-1)u /c 2 u 2 /c 2 = 1

Summary We have developed a tool that for the first time can produce self-consistent simulations of lower hybrid current drive in toroidal geometry using the full wave approach and 3D Fokker-Planck. Spectral broadening effects due to diffraction and poloidal mode coupling are included in the model. The full wave calculation yields the electric fields directly. Wave fronts are calculated properly near caustics and cutoffs. This is may be important in the multipass damping regime. 22

References Brambilla, M., Numerical simulation of ion cyclotron waves in tokamak plasmas, Plasma Phys. Control. Fusion 41, (1999), 1. Wright, J.C., Bonoli, P.T., Brambilla, M., et al., Full wave simulations of fast wave mode conversion and lower hybrid wave propagation in tokamaks, Phys. Plasmas 11, (2004), 2473. Wright, J.C., Valeo, E.J., Phillips, C.K., Bonoli, P.T. and Brambilla, M., Commun. Comput. Phys., 4, (2008), 545 Wright, J.C., Valeo, E.J., Phillips, C.K., Bonoli, P.T. and Brambilla, M. Physics of Plasmas, 16 July (2009) Harvey, R.W. & McCoy, M.G. The CQL3D Fokker-Planck Code Proc. of the IAEA Tech. Committee Meeting (Montreal,1992), Institute of Physics Publishing; USDOC/NTIS Doc. DE93002962, 1993, 489-526 Bertelli, N.; Pereverzev, G.V. & Poli, E. Beam Tracing description of LH waves in tokamaks 34th EPS Plasma Physics Conference, 2007 Rodrigues, P. & Bizarro, J.P.S. Images of Electrostatic Lower-Hybrid-Wave Beam Propagation in Tokamak Plasmas Using a Paraxial WKB Approach- IEEE TRANSACTION ON PLASMA SCIENCE, 2002, 30, 68-69 Keller, J.B. Geometrical Theory of Diffraction JOURNAL OF THE OPTICAL SOCIETY OF AMERICA, 1962, 52, 116-130 Felsen, L.B. Quasi-optical Methods in Microwave Propagation and Diffraction, Applied Optics, 1965, 4, 1217-1229 23

Comparison of fe(v) Contour plot of distribution function γ v c 0.8 0.4 0-1 -0.5 0 0.5 1 1.5 2 γ v // c Ray tracing Relativistic distribution functions.