Heat flux transported by fast electrons in front of lower hybrid wave antenna on EAST tokamak

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

Diamond Neutral Par0cles Spectrometer at JET and proposal for ITER

LH Generated Hot Spots on the JET Divertor

Overview the CASTOR Fast Particles experiments

Overview of EAST Experiments on the Development of High-Performance Steady- State Scenario

Recent Experiments of Lower Hybrid Wave-Plasma Coupling and Current

Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak

Infernal modes and physical interpreta3on of the edge harmonic oscilla3ons in tokamak QH mode discharges

PHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China.

Experimental results with the Cooled Lithium Limiter (CLL) on FTU

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

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

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

Plasma Wall Interactions in Tokamak

Ray Tracing and Full-wave Simulation of KSTAR LH Wave

27th IAEA Fusion Energy Conference Ahmedabad, India. October 22 27, 2018

Electron Transport and Improved Confinement on Tore Supra

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

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER

Long Distance Coupling of Lower Hybrid Waves in JET using Gas Feed

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France

Evolution of Bootstrap-Sustained Discharge in JT-60U

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

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

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan

for the French fusion programme

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

TOKAMAK EXPERIMENTS - Summary -

Divertor Requirements and Performance in ITER

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

A Kinetic Theory of Planar Plasma Sheaths Surrounding Electron Emitting Surfaces

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

Snakes and similar coherent structures in tokamaks

Critical Physics Issues for DEMO

Fast ion physics in the C-2U advanced, beam-driven FRC

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

Modelling of plasma edge turbulence with neutrals

Theory Work in Support of C-Mod

Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East

DT Fusion Power Production in ELM-free H-modes in JET

Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants

Comments About Varied IEC Approaches to Fusion Power

P.Jacquet*, P.Bibet, P.Froissard, G.Rey, F.Surle, M.Tareb. Centre d' 6tudes de Cadarache Association Euratom-CEA

Application of atomic data to quantitative analysis of tungsten spectra on EAST tokamak

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

Development of LH wave fullwave simulation based on FEM

Neutral beam plasma heating

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

Nuclear Fusion and ITER

Cosmic Ray Electrons with CTA. R.D. Parsons

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

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

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

Overview Impact of 3D fields (RMP) on edge turbulence and turbulent transport

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff

RELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE

INTEGRATED OPERATION OF STEADY-STATE LONG PULSE H-MODE IN EAST

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

Laser- Accelerated Proton Beams and their Medical Applica6ons. By Eric Sacks

Disruption mitigation in ITER

Additional Heating Experiments of FRC Plasma

Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor

Developing Steady State ELM-absent H-Mode scenarios with Advanced Divertor Configuration in EAST tokamak

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

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

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

C-Mod Advanced Tokamak Program: Recent progress and near-term plans

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

Impact of H&CD Technology on DEMO Scenario Choice (Impact of DEMO Scenario on Choice of H&CD Technology)

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

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Concept of Multi-function Fusion Reactor

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

and expectations for the future

ITER A/M/PMI Data Requirements and Management Strategy

Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC

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

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

Plan of Off-axis Neutral Beam Injector in KSTAR

ENEA for EUROfusion, via E. Fermi 45, Frascati (Rome), Italy 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, , China 3

RECENT PROGRESSES ON HIGH PERFORMANCE STEADY-STATE PLASMAS IN THE SUPERCONDUCTING TOKAMAK TRIAM-1M

Overview of Recent Results from Alcator C-Mod including Applications to ITER Scenarios

Focus On : JET Plasma Heating and Current Drive

Correlations of ELM frequency with pedestal plasma characteristics

Chapter IX: Nuclear fusion

Role of Magnetic Configuration and Heating Power in ITB Formation in JET.

Density Peaking At Low Collisionality on Alcator C-Mod

First Experimental Results with the ITER-Relevant Lower Hybrid Current Drive Launcher in Tore Supra

History of Mechanical Engineering for Fusion Research at Princeton

Mo#va#on J B = P. Magne&cally confined fusion devices require detailed &meresolved measurement of J(r) and B(r):

PIC/MCC Simulation of Radio Frequency Hollow Cathode Discharge in Nitrogen

MHD. Jeff Freidberg MIT

ICRH Experiments on the Spherical Tokamak Globus-M

Progress in understanding W control using ICRH in the JET-ILW tokamak

Progress Toward High Performance Steady-State Operation in DIII D

Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas

Analysis of Ion Cyclotron Heating Issues for ITER

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads

Transcription:

Heat flux transported by fast electrons in front of lower hybrid wave antenna on EAST tokamak Nong Xiang 1, 2 In collaboration with Zhongzheng Men 1, 2, Jing Ou 1, 2,Xueyi Wang 3, Chunyun Gan 1, 2 1 Ins&tute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China 2 Center for Magne&c Fusion Theory, Chinese Academy of Sciences, China 3 Physics Department, 206 Allison Laboratory, Auburn University, USA 8 th IAEA Technique Mee0ng Theory of Plasma instabili0es, June.12-14, 2017 Vienna, Austria

Outline Background and mo0va0on Par0cle-in-cell simula0on model 1) fast electrons 2) Secondary electrom emission Simula0on results Summary & discussions 2

Steady state scenarios are strongly desired by Tokamak reactors for which rf wave hea8ng and current drive is very important Ø ITER will have the first plasma in 2025. CFETR has been finished with conceptual design and begun engineering tests. Ø Steady state discharge is one of the main opera0on scenarios for ITER and CFETR. Lower hybrid current drive is a promising method sustaining plasma current and controlling current profile. ITER 3

EAST primary goal in 5 years: 400s steady state opera8on with 50% Boot strap current Ø Long pulse SS (>400s) H mode discharges with more than 50% boot strap current will be achieved on EAST in next 5 years. Steady state opera0ons on EAST are ozen stopped by accumula0on of impuri0es and lose of density control. Hot spots ozen observed in LHCD with high input power becomes the bo\leneck for realizing long pulse SS discharges on EAST! 4

Hot spots observed during LHCD experiments have seriously degraded EAST discharges Hotspots related to LHW launcher are generally observed. As P(f=4.6Ghz) >2MW, hot spots are observed 1) LH antenna guard limters are damaged badly 2) A lot of impuri0es are generated which degrade opera0ons Hot spots during LHCD are observed also on JET, Tore Supra, TdeV, ASDEX etc..

Mechanism for hot spot produc8ons: fast electron effects Ø Hot spots are caused by strong heat fluxes flowing to walls. Ø Why are strong heat fluxes produced during lower hybrid current drive? Fast electrons are responsible for the strong heat flux! (Rantamaki et al.nf 2000; Li et al. POP 15, Gunn et al. NF 2016) 6

Fast electrons generated by interac8ons of electrons and high n // modes Ø Electrons in the SOL interact with high-n // LH modes Ø The resonances can overlap as the input power is sufficiently high, resul0ng in forma0on of quasi-linear plateau Ø A frac0on of energy absorbed is deposited into limiters carried by fast electrons, giving rise to a large heat flux and cause the hot spots (only fast electrons ma\er!). (Rantamaki et al.nf 2000; Li, POP2015) (Rantamaki et al.nf 2000) 7

What is missed in the previous studies? Ø Sheaths natured formed in front of the limiter walls are neglected in es0ma0ng the heat flux to the walls. Sheaths are important! Why? 1) A sheath can distribute the heat flux carried by electrons and ions to walls 2) Presence of fast electrons can affect sheath structure, which in turn changes the heat fluxes of electrons and ions. It is a mul0-scale issues (fast electrons, background electrons, ions)! 8

Simula8on model (I) A PIC code GCPIC is developed to calculate the heat flux to the limiter, which includes sheaths. Plasma is confined between two limiters at x=0 and x=l. Parameters: L=0.2m (5396λD ) n0 = 1018m-3 Te= 25ev Model includes: 1. Fast electrons produced by resonant electron-wave interac0ons. 2. Secondary electron emissions at the limiter surfaces. 9

Simula8on model (II) Ø Fast electron model due to lower hybrid wave (Fisch 1978) f (u) = n 0 e 0.5u 2, u < u 1 or u > u 2 2π v te C 0 e wdw 1+Dw 3, u 1 < u < u 2 Ø Secondary electron emission yield δ(e 0 ) = δ m E 0 E m exp(2 2 E 0 E m ). δ m =0.7 (C), 0.9(W), E m = 350eV (C), 600eV(W) 10

Heat flux to limiters without fast electrons (theory) Ø The sheath expels electrons and accelerates ions, Ø For Maxwellian electrons & ions, floa0ng poten0al between the sheath edge and walls ϕ f 2.5T e Electrons wall Heat flux to walls: q e q i 0.2n 0 C s T e For n 0 =10 18 m 3,T e = 25ev, q e 0.5MW / m 2 ions Without fast electrons the heat flux to the limiter is small! 11

Results without fast electrons agree with sheath theory Ø Floa0ng poten0al and heat flux agree with theore0cal result. Electron and ion densities (top), and potential (bottom) as a function of the normalized distance for maxwellian electrons and ions. The sheath edge is indicated by the vertical line. Electron (a), ion velocity distribution function (b) and heat flux at x = 5394λ D. 12

Physical insight of fast electron effects Ø A sheath is formed to balance the par0cle fluxes. The sheath poten0al should be increased to reduce the fast electron flux. J e + J f = J i J e n 0 exp( eφ f / T e ), J f αn 0 exp( eφ f / T f ), T f >> T e J i n 0 C s. (Stangeby PPCF 95) Ø The ion heat flux is significantly increased. Ion energy at the wall, E i = T e φ f, eφ f >> T e, q i eγ i φ f >> q i,0 (without fast electrons, proportional to density) Fast electron energy at the wall, E f = T f +φ f q f eγ i E f < q i 13

Results in the presence of fast electrons but without SEE(I) Ø Loading the electrons with a quasi-linear plateau giving driven current J ~ 40KA/m 2 in the plasma Electron VDF in plasma region Ø Sheath poten0al is enhanced by nearly one order higher. 14

Results in the presence of fast electrons but without SEE(II) Ø Background electrons are repelled from sheath, but fast electrons can penetrate, giving a slow decay density profile. Electron VDF near the limiter surface Ø Ion heat flux is enhanced and exceed the electron heat flux. Total heat flux is increased by one order higher! Consistent with analysis 15

Effects of secondary electron emissions (I) Ø Secondary electrons emission (SEE) reduces the fast electron current, thus reduce sheath poten0al too. J e + J f = J i J e n 0 (1 δ e )exp( eφ f / T e ), J f αn 0 (1 δ f )exp( eφ f / T f ), T f >> T e J i n 0 C s. Ø SEE strongly depends on materials. Consider C and W Electron energy distribu0on at wall 16

Effects of secondary electron emissions (II) Ø Sheath poten0als are reduced with SEE. Ø Sheath width decreases with SEE. Ø Ion heat flux is comparable to electron s Total heat flux is about 8MW/m2 which may cause hot spot! 17

Summary & Discussions Ø The sheath is important in the calcula0on of electron and ion heat fluxes. The presence of fast electrons can significantly increase the sheath poten0al. The resul0ng sheath field can significantly accelerate ions which causes enhancement of ion and electron heat fluxes and make the ion heat flux comparable to the electron s. For typical LHCD parameters on EAST, the total heat flux > 8MW/m 2, responsible for hot spots observed. In addi0on, the energe0c ions may produce heavily spu\ering and damage the walls. Ø The secondary electron emission can reduce sheath poten0al, increasing the electron heat flux. The total heat flux to the limiter walls remains nearly the same. 18