Effect of neoclassical poloidal viscosity and resonant magnetic perturbation on the response of the m/n=1/1 magnetic island in LHD

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

Multifarious Physics Analyses of the Core Plasma Properties in a Helical DEMO Reactor FFHR-d1

Non-linear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade

Extension of High-Beta Plasma Operation to Low Collisional Regime

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device

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

MHD Simulation of High Wavenumber Ballooning-like Modes in LHD

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

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

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

Role of Low-Order Rational Surfaces in Transport Barrier Formation on the Large Helical Device

Neoclassical transport

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

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

Particle Pinch Model of Passing/Trapped High-Z Impurity with Centrifugal Force Effect )

Experimental analysis and predictive simulation of heat transport using TASK3D code

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

Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD )

Toroidal confinement devices

Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea (Kyoto University, Uji, Japan, 26-28

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device

Shear Flow Generation in Stellarators - Configurational Variations

Energetic-Ion Driven Alfvén Eigenmodes in Large Helical Device Plasmas with Three-Dimensional Structure and Their Impact on Energetic Ion Transport

Tokamak/Helical Configurations Related to LHD and CHS-qa

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas

A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal. W. M. Stacey

R B. Here the first term represents

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

EUROFUSION WPJET1-PR(16) CG Albert et al.

Coexistence of the drift wave spectrum and low-frequency zonal flow potential in cylindrical laboratory plasmas

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

Ion plateau transport near the tokamak magnetic axis. Abstract

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Nonlinear MHD effects on TAE evolution and TAE bursts

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison

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

Nonlinear Simulation of Energetic Particle Modes in JT-60U

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

Hybrid Kinetic-MHD simulations with NIMROD

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

Predicting the Rotation Profile in ITER

Current-driven instabilities

Inter-linkage of transports and its bridging mechanism

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

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

GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D

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

Bootstrap Current Simulations with Experimental LHD Plasma Density and Temperature Profiles, Energy Scattering and Finite Orbit Width

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

Guiding Center Orbit Studies in a Tokamak Edge Geometry Employing Boozer and Cartesian Coordinates

Rotation and Neoclassical Ripple Transport in ITER

MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

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

Nonlinear magnetohydrodynamic effects on Alfvén eigenmode evolution and zonal flow

On the physics of shear flows in 3D geometry

Simulation Research on disruptions and runaway electrons

Simulation Study of High-Frequency Magnetosonic Waves Excited by Energetic Ions in Association with Ion Cyclotron Emission )

High-m Multiple Tearing Modes in Tokamaks: MHD Turbulence Generation, Interaction with the Internal Kink and Sheared Flows

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

Hybrid Kinetic-MHD simulations with NIMROD

Gyrokinetic theory for particle transport in fusion plasmas

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

Fast Ion Confinement in the MST Reversed Field Pinch

Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak

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

Ion orbits and ion confinement studies on ECRH plasmas in TJ-II stellarator

arxiv: v1 [physics.plasm-ph] 11 Mar 2016

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

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

Triggering Mechanisms for Transport Barriers

Enhancement of helium exhaust by resonant magnetic perturbation fields at LHD and TEXTOR

Development of a High-Speed VUV Camera System for 2-Dimensional Imaging of Edge Turbulent Structure in the LHD

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

TURBULENT TRANSPORT THEORY

The Role of Dynamo Fluctuations in Anomalous Ion Heating, Mode Locking, and Flow Generation

1 EX/P5-9 International Stellarator/Heliotron Database Activities on High-Beta Confinement and Operational Boundaries

Electrode Biasing Experiment in the Large Helical Device

Resistive Wall Mode Control in DIII-D

Density Collapse in Improved Confinement Mode on Tohoku University Heliac

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

GA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J.

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

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

GA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY

Modelling of the penetration process of externally applied helical magnetic perturbation of the DED on the TEXTOR tokamak

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

Reduced-Size LHD-Type Fusion Reactor with D-Shaped Magnetic Surface )

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

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

Experimental evaluation of nonlinear collision effect on the beam slowing-down process

Transport, Damping, and Wave-Couplings from Chaotic and Collisional Neoclassical Transport

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

TOROIDAL PHASING OF RESONANT MAGNETIC PERTURBATION EFFECT ON EDGE TRANSPORT IN THE DIII-D TOKAMAK

14. Energy transport.

Confinement Study of Net-Current Free Toroidal Plasmas Based on Extended International Stellarator Database

MHD. Jeff Freidberg MIT

arxiv: v1 [physics.plasm-ph] 10 Jun 2017

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

MHD Linear Stability Analysis Using a Full Wave Code

Transcription:

Effect of neoclassical poloidal viscosity and resonant magnetic perturbation on the response of the m/n=1/1 magnetic island in LHD B. Huang 1, S. Satake 2, R. Kanno 2, Y. Narushima 2, S. Sakakibara 2, S. Ohdachi 2, and LHD experiment group 1 The Graduate University for Advanced Studies[SOKENDAI] 2 National Institute for Fusion Science Plasma conference 214, Nov, 181, 214 B. Huang et. al. (SOKENDAI) 1 / 17

Outline 1 Abstract 2 The Motivation of this work 3 Simulation with FORTEC-3D 4 Simulation Results Radial Profile of NPV and E r 5 Simulation Results Radial Profile of NPV and E r NPV density dependence on R-axis ( @ ι 1 surface) Depandence of NPV on E r and Collisionality 6 Simulation Results with RMP NPV density on R-axis Depandence of NPV (each (m,n) mode) 7 Conclusion and Future work B. Huang et. al. (SOKENDAI) 2 / 17

Abstract We employ FORTEC-3D to investigate the dependence of neoclassical poloidal viscosity(npv) on magnetic configuration of LHD, and the effect of resonant magnetic perturbation (RMP) on NPV. For the m/n = 1/1 island formation in LHD, the threshold of RMP amplitude depends on the magnetic axis position in LHD. On the other hand, neoclassical transport theory predicts that the NPV also correlates to the magnetic axis position. By δf simulation, we investigate NPV variation in LHD plasmas with plasma profiles and ambipolar electric field E r. Thus, we study m/n=1/1 RMP effect on NPV. B. Huang et. al. (SOKENDAI) 3 / 17

RMP pentrates plasma as its amplitude exceeds the threshold. m/n = 1/1 RMP in LHD 1 RMP penetrate plasma as perturbation amplitude exceeds threshold. 2 The threshold correlates to magnetic axis position. 3 The Neoclassical Poloidal viscosity (NPV) also depends on magnetic axis position. With LHD experiment data (temperature, density, R ax ), we investigate the basic dependence of NPV in LHD. B. Figure Huang et. 1: al. Rax-RMP (SOKENDAI) amplitude 4 / 17

Simulate NPV with FORTEC-3D We employ drift-kinetic equation for distribution function δf(x,v) f(x,v) f m (x,v) δf t +(v +v D ) δf + v f v C T(δf) = (v D + v v )f m +Pf m. Taking the moment of (1) (1) t mnu e θ = e θ P +e nu Φ (2) NPV is difined as e θ P δp B. (3) B θ FORTEC-3D simulates drift kinetic Eq. and evaluate the δp δp = δp +δp δp = d 3 v m 2 v 2 δf, δp = d 3 v mv 2 δf B. Huang et. al. (SOKENDAI) 5 / 17

Simulation Result We scan the magnetic axis from 3.55[m] to 3.8[m] for ramped-up/down RMP experiments respectively as we show in the fig.(1). In the fig.(2) We investigate NPV amplitude and E r radial profiles without RMP. We simulate the ambipolar radial electric field E r on flux surface by using Γ i (from FORTEC-3D) and Γ e (from GSRAKE[4]). For the investigation of NPV without RMP effect, we collect the data when RMP was shielded. B. Huang et. al. (SOKENDAI) 6 / 17

Simulation Results Scan the magnet axis from 3.55[m] to 3.8[m] by FORTEC-3D NPV[N/m 2 ] NPV [N/m 2 ].5 -.5-1 -1.5 LHD RMP-ramp-up Er 116765, R=3.55-6 116765, R=3.55.5 116761, R=3.6 118891, R=3.6 118891, R=3.6-8 116761, R=3.6-3 116738, R=3.65 116738, R=3.65-3.5 116735, R=3.7-1 116735, R=3.7 121762, R=3.75 121762, R=3.75 116727, R=3.8 116727, R=3.8-4 -12.3.4.5.6.7.8.9 1.3.4.5.6.7.8.9 1 fig(2a) Radial profile of NPV in ramp-up cases fig.(2b) Radial profile of E r in ramp-up cases -.5-1 -1.5 LHD RMP-ramp-down 2-4 LHD RMP-ramp-up -4.5-3 -6 R365 (116785) R365 (116785) -3.5 R365 (116788) -8 R365 (116788) -4 R37 (116791) R37 (116791) R375 (116795) -1 R375 (116795) -4.5 R38 (11684) R38 (11684) R36 (118888) R36 (118888) -5-12.3.4.5.6.7.8.9 1.3.4.5.6.7.8.9 1 fig(2c) Radial profile of NPV in ramp-down cases fig.(2d) Radial profile of E r in ramp-down cases E r [kv/m] 2 LHD RMP-ramp-down B. Huang et. al. (SOKENDAI) Figure 2: Radial Profile of NPV and E. 7 / 17

Simulation Results NPV density depends on E r ( @ ι 1 surface) NPV[norm. by r * dp/dr] -.1 -.8 -.6 -.4 -.2 116795 118888 116788 121781 116791 11684 116738 116785 116735 116761 116727 118891 116765 up down 121762 NPV[norm. by r * dp/dr] -.1 -.8 -.6 -.4 -.2 116727 118891 121762 116765 up down 118888 116795 121781 116788 11684 116791 116738 116785 116735 116761.4.5.6.7.8.9 1 1.1 1.2 1.3 1.4 nu* -5-4.5-4 -3.5-3.5-1.5-1 -.5 Er Figure 3: ν -NPV. Figure 4: Dependence of NPV on E r B. Huang et. al. (SOKENDAI) 8 / 17

Simulation Results NPV depends on R ax but Collisionality NPV[norm. by r * dp/dr] -.1 -.8 -.6 -.4 118888 116788 116761 -.2 118891 116727 116765 3.5 3.55 3.6 3.65 3.7 3.75 3.8 3.85 Rax up down 116795 121781 116791 11684 116738 116785 116735 121762 Figure 5: Dependence of NPV on R ax We expected that NPV 1 nu,but in fig.(3), the collisionality is not the major factor dominating the amplitude of NPV. As neoclassical theory expected, the fig.(4) shows that the NPV amplitude is proportional to 1/ E r. In the fig.(5), NPV increases as R ax increases but it is still determined by plasma profile, too. For example, density and ion temperature may be the potential factor. For shot#116727, NPV amplitude decreases due to large E r amplitude. For shot#11888, NPV is increased but E r amplitude is small. B. Huang et. al. (SOKENDAI) 9 / 17

Simulation Results with RMP NPV density on R-axis NPV [N/m 2 ] -.7 -.6 -.5 -.4 -.3 LHD 116765t5178 (R ax =3.55) m/n=1/1 RMP -.2 w/o RMP db=.1% -.1 db=.3% db=1.% db=3.%.5.6.7.8.9 1 Figure 6: Radial profile of NPV with RMP in a case R ax = 3.55 NPV [N/m 2 ] -1 -.8 -.6 -.4 -.2 LHD 118891t4848 (R ax =3.6) m/n=1/1 RMP (db=.1%) (db=.3%) (db=1.%) (db=3.%) iota=1.5.6.7.8.9 1 Figure 7: Radial profile of NPV with RMP in a case R ax = 3.6 B. Huang et. al. (SOKENDAI) 1 / 17

Simulation Results with RMP NPV density on R-axis NPV [N/m 2 ] -3.5-3.5 LHD 116735t5233 (R ax =3.7) m/n=1/1 RMP -1.5 w/o RMP db=.1% -1 db=.3% db=1.% db=3.% -.5.5.6.7.8.9 1 Figure 8: Radial profile of NPV with RMP in a case R ax = 3.7 In figs.(6), (7) and (8), we investigate the NPV with different m/n= 1/1 RMP amplitude using a simple model δb () 2. The RMP effect is obvious near m/n= 1/1 surface. We found that below 1% δb/b amplitude, NPV in LHD is almost unaffected by the RMP field. B. Huang et. al. (SOKENDAI) 11 / 17

Simulation Results Depandence of NPV (each (m,n) mode) (1,) NPV[N/m^2] -.8 -.9-1 -1.1-1.2-1.3-1.4-1.5-1.6 =.69 =.79 =.89, iota=1.1.1-1.2-1.3-1.4-1.5-1.6-1.7-1.8-1.9.1.2.1.1 -.8-1.2-1 -1.4-1.6-1.8.2.4.6.1.1 (1,1) NPV[N/m^2] -.1 -.2 -.3 -.4 -.5 -.6 -.7 -.8.1.1.6.4.2 -.2 -.4 -.6 -.8 -.1 -.12 -.14.1.1 -.1 -.2 -.3 -.4 -.5 -.6 -.7 3.55 3.6 3.7.1.1 (2,1) NPV[N/m^2] 1.4 1.3 1.2 1.1.9 1.8.7.6.5.4.3.1.1 1.3 1.25 1.2 1.15 1.1 1.5 1.1.1 2 1.8 1.6 1.4 1.2 1.8.6.4.1.1 delta B delta B delta B Figure 9: Depandence of NPV at B(1,), B(1,1) and B(2,1) mode B. Huang et. al. (SOKENDAI) 12 / 17

Simulation Results Depandence of NPV (each (m,n) mode) B amplitude.4.3.2.1 -.1 -.2 R=3.55 (1,) (2,1) (1,1) (3,1) R=3.6 (1,) (2,1) (1,1) (3,1) R=3.7 (1,) (2,1) (1,1) (3,1).1.2.3.4.5.6.7.8.9 1 Figure 1: B m,n amplitudes in R ax = 3.7, R ax = 3.65 and R ax = 3.55. In fig.1, B 1, and B 2,1 are main components.the tow components are changed a little due to the shift in Rax. By contrast, B 1,1 and B 3,1 are minor but changed a lot due to the shift in Rax. In fig.11, NPV 1, and NPV 2,1 sum is small to contribute to total NVP too much. In Fig.12, NPV 1,1 and NPV 3,1 sum is main contribution for NPV. B. Huang et. al. (SOKENDAI) 13 / 17

Simulation Results Depandence of NPV (each (m,n) mode) NPV[N/m 2 ] 2 1-1 NPV 1,,R=3.55 R=3.6 R=3.7 NPV 2,1,R=3.55-3 R=3.6 R=3.7-4 NPV 1, +NPV 2,1 R=3.55 R=3.6 R=3.7-5.1.2.3.4.5.6.7.8.9 1 Figure 11: NPV contribution of B(1,) and B(2,1) without RMP in R ax = 3.7, R ax = 3.65 and R ax = 3.55. NPV[N/m 2 ] 1.5 -.5-1 -1.5 NPV tot, R=3.55 R=3.6 R=3.7 NPV.5 (1,1) +NPV (3,1) R=3.55 R=3.6 R=3.7-3.1.2.3.4.5.6.7.8.9 1 Figure 12: NPV contribution of B(1,1) and B(3,1) without RMP in R ax = 3.7, R ax = 3.65 and R ax = 3.55. B. Huang et. al. (SOKENDAI) 14 / 17

Depandence of NPV (each (m,n) mode) We construct the NPV by e θ P = e θ P m,n B nδ m,n Q m,n. (4) m,n m,n 1 As expected, the RMP, mode B(1,1), affects surface ι 1 and the effect is proportional to RMP amplitude. 2 In the other surface (=.69 and.79), it is small and negligible to the RMP effect on mode B(1,1). The strong RMP influences the (1, )- and (2, 1)- modes and changes their amplitudes. This suggests that the strong RMP δb m,n couple with the pressure perturbation of the different modes, Q m,n. 3 Practically δb/b 1 4 in LHD but we employ δb/b 1 2 in our test. It is anticipated that the RMP field does not change NPV amplitude in the practical LHD experiment. B. Huang et. al. (SOKENDAI) 15 / 17

Conclusion and Future work Conclusion NPV amplitude becomes larger as R ax moves outward. Following the results, we are able to see the influence near the resonant surface (ι 1) if the RMP amplitude δb/b >.1. Practically RMP amplitude is δb/b 1 4 in LHD. We found that m/n = 1/1 RMP less than 1% cannot affects NPV. The strong RMP influences the mode B(1,) and B(2,1) and changes their amplitudes. Future work Study the relation between the NPV torque with the threshold RMP amplitude from the LHD experiments. Compare the E r profile obtained from the ambipolar condition with the measured. B. Huang et. al. (SOKENDAI) 16 / 17

Referece and Acknowledgment Referece [1] Sakakibara,et al.,(213). In Nuclear Fusion 53, p. 431. [2] Narushima, Y.,et al.,(211). In Nuclear Fusion 51, p. 833. [3] Satake, S.,et al.(211). In Plasma Physics and Controlled Fusion 53, p. 5418. [4] C D Beidler and W D D haeseleer (1995) Plasma Phys. Control. Fusion 37 463 Acknowledgment This work is pported by NIFS collaborative Research Programs NIFS13KNST51, and JSPS Grant-in-Aid for Young Scientists (B), No. 237681. Part of calculations was carried out using the HELIOS supercomputer at IFERC-CSC, under the ITER-BA collaboration implemented by Fusion for Energy and JAEA. This presentation received the financial support program for international conference presentations provided by the Course-by-Course Education Program of SOKENDAI. B. Huang et. al. (SOKENDAI) 17 / 17