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

Size: px
Start display at page:

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

Transcription

1 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 , 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

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

3 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 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

4 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

5 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..

6 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

7 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

8 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

9 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

10 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

11 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

12 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

13 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

14 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

15 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

16 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

17 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

18 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

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

Integrated modeling of LHCD non- induc6ve scenario development on Alcator C- Mod Integrated modeling of LHCD non- induc6ve scenario development on Alcator C- Mod S. Shiraiwa, P. Bonoli, R. Parker, F. Poli 1, G. Wallace, and J, R. Wilson 1 PSFC, MIT and 1 PPPL 40th European Physical

More information

Diamond Neutral Par0cles Spectrometer at JET and proposal for ITER

Diamond Neutral Par0cles Spectrometer at JET and proposal for ITER Diamond Neutral Par0cles Spectrometer at JET and proposal for ITER V. Krasilnikov, V. Amosov, Yu Kaschuck, N. Marcenko, A. Krasilnikov. (TRINITI, Russia) I. Coffey, S. Popovichev, M. Beldishevski (EFDA

More information

LH Generated Hot Spots on the JET Divertor

LH Generated Hot Spots on the JET Divertor LH Generated Hot Spots on the JET Divertor K.M. Rantamäki 1, V. Petržílka 2, F. Žáček 2, A. Ekedahl 3, K. Erents 4, V. Fuchs 2, M. Goniche 3, G. Granucci 5, S.J. Karttunen 1, J. Mailloux 4, and M.-L.Mayoral

More information

Overview the CASTOR Fast Particles experiments

Overview the CASTOR Fast Particles experiments Overview the CASTOR Fast Particles experiments F. Zacek 1, V. Petrzilka 1, M. Goniche 2, P. Devynck 2, J. Adamek 1 1 Association Euratom/IPP.CR, Za Slovankou 3, 182 21 Prague 8, Czech Republic 2 Association

More information

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

Overview of EAST Experiments on the Development of High-Performance Steady- State Scenario 26th IAEA FEC, 17-22 October 2016, Kyoto Japan Overview of EAST Experiments on the Development of High-Performance Steady- State Scenario B.N. Wan on behalf of EAST team & collaborators Email: bnwan@ipp.ac.cn

More information

Recent Experiments of Lower Hybrid Wave-Plasma Coupling and Current

Recent Experiments of Lower Hybrid Wave-Plasma Coupling and Current 1 EXW/P7-3 Recent Experiments of Lower Hybrid Wave-Plasma Coupling and Current Drive in EAST Tokamak B J Ding 1), Y L Qin 1), W K Li 1), M H Li 1), E H Kong 1), A Ekedahl ), Y Peysson ), M Wang 1), H D

More information

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

Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak Dr. Jawad Younis Senior Scientist Pakistan Atomic Energy Commission, P. O. Box, 2151,Islamabad Institute

More information

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

Infernal modes and physical interpreta3on of the edge harmonic oscilla3ons in tokamak QH mode discharges Infernal modes and physical interpreta3on of the edge harmonic oscilla3ons in tokamak QH mode discharges Linjin Zheng, M. Kotschenreuther, and P. Valanju Ins3tute for Fusion Studies University of Texas

More information

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

PHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China. PHYSICS OF CFETR Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China Dec 4, 2013 Mission of CFETR Complementary with ITER Demonstration of fusion

More information

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

Experimental results with the Cooled Lithium Limiter (CLL) on FTU Experimental results with the Cooled Lithium Limiter (CLL) on FTU Giuseppe Mazzitelli ENEA Technological Fusion Division The First IAEA Technical Mee

More information

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

Full-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak Full-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak P. T. BONOLI, J. P. LEE, S. SHIRAIWA, J. C. WRIGHT, MIT-PSFC, B. DING, C. YANG, CAS-IPP, Hefei 57 th Annual Meeting of the APS

More information

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

Recent results from lower hybrid current drive experiments on Alcator C-Mod Recent results from lower hybrid current drive experiments on Alcator C-Mod R. R. Parker, S.-G. Baek, C. Lau, Y. Ma, O. Meneghini, R. T. Mumgaard, Y. Podpaly, M. Porkolab, J.E. Rice, A. E. Schmidt, S.

More information

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

Predictive Study on High Performance Modes of Operation in HL-2A 1 1 EX/P-0 Predictive Study on High Performance Modes of Oration in HL-A 1 Qingdi GAO 1), R. V. BUDNY ), Fangzhu LI 1), Jinhua ZHANG 1), Hongng QU 1) 1) Southwestern Institute of Physics, Chengdu, Sichuan,

More information

Plasma Wall Interactions in Tokamak

Plasma Wall Interactions in Tokamak Plasma Wall Interactions in Tokamak Dr. C Grisolia, Association Euratom/CEA sur la fusion, CEA/Cadarache Outline 1. Conditions for Fusion in Tokamaks 2. Consequences of plasma operation on in vessel materials:

More information

Ray Tracing and Full-wave Simulation of KSTAR LH Wave

Ray Tracing and Full-wave Simulation of KSTAR LH Wave Ray Tracing and Full-wave Simulation of KSTAR LH Wave 2016 KO-JA Workshop on Physics and Technology of Heating and Current Drive Presented by Young-soon Bae NFRI a W. Namkung, a M.H. Cho, b S. Shiraiwa,

More information

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

27th IAEA Fusion Energy Conference Ahmedabad, India. October 22 27, 2018 Advances in Runaway Electron Control and Model Validation for ITER by C. Paz-Soldan1 with contributions from: N. Eidietis,1 E. Hollmann,2 A. Lvovskiy,3 C. Cooper,3 J. Herfindal,4 R. Moyer,2 D. Shiraki,4

More information

Electron Transport and Improved Confinement on Tore Supra

Electron Transport and Improved Confinement on Tore Supra Electron Transport and Improved Confinement on Tore Supra G. T. Hoang, C. Bourdelle, X. Garbet, T. Aniel, G. Giruzzi, M. Ottaviani. Association EURATOM-CEA. CEA-Cadarache, 38, St Paul-lez-Durance, France

More information

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

Advanced Tokamak Research in JT-60U and JT-60SA I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development

More information

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

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER D. BOUCHER 1, D. MOREAU 2, G. VAYAKIS 1, I. VOITSEKHOVITCH 3, J.M. ANÉ 2, X. GARBET 2, V. GRANDGIRARD 2, X. LITAUDON 2, B. LLOYD

More information

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

Long Distance Coupling of Lower Hybrid Waves in JET using Gas Feed JET R(97)1 Long Distance Coupling of Lower Hybrid Waves in JET using Gas Feed M Goniche 1, J A Dobbing, A Ekedahl, P Schild, F X Söldner. JET Joint Undertaking, Abingdon, Oxfordshire, OX1 3EA, 1 Centre

More information

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

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U EX1-4 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase, a S. Ide, b Y. Kamada, b H. Kubo, b O. Mitarai, c H. Nuga, a Y. Sakamoto, b T. Suzuki, b H. Takenaga, b and the JT-60 Team a University

More information

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

Lower Hybrid RF: Results, Goals and Plans. J.R. Wilson Alcator C-Mod Program Advisory Meeting January 27, 2010 Lower Hybrid RF: Results, Goals and Plans J.R. Wilson Alcator C-Mod Program Advisory Meeting January 27, 2010 ITER Needs and the RENEW Report Provide a Context for LH Research on C-Mod ITER Needs: Hea-ng

More information

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

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod

More information

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

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan The Sun Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan 2017 CNS Conference Niagara Falls, June 4-7, 2017 Tokamak Outline Fusion

More information

for the French fusion programme

for the French fusion programme The ITER era : the 10 year roadmap for the French fusion programme E. Tsitrone 1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France Association EURATOM-CEA TORE

More information

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

Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device P. T. Bonoli, Y. Lin. S. Shiraiwa, G. M. Wallace, J. C. Wright, and S. J. Wukitch MIT PSFC, Cambridge, MA 02139 59th Annual Meeting

More information

TOKAMAK EXPERIMENTS - Summary -

TOKAMAK EXPERIMENTS - Summary - 17 th IAEA Fusion Energy Conference, Yokohama, October, 1998 TOKAMAK EXPERIMENTS - Summary - H. KISHIMOTO Japan Atomic Energy Research Institute 2-2 Uchisaiwai-Cho, Chiyoda-Ku, Tokyo, Japan 1. Introduction

More information

Divertor Requirements and Performance in ITER

Divertor Requirements and Performance in ITER Divertor Requirements and Performance in ITER M. Sugihara ITER International Team 1 th International Toki Conference Dec. 11-14, 001 Contents Overview of requirement and prediction for divertor performance

More information

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

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory The Path to Fusion Energy creating a star on earth S. Prager Princeton Plasma Physics Laboratory The need for fusion energy is strong and enduring Carbon production (Gton) And the need is time urgent Goal

More information

A Kinetic Theory of Planar Plasma Sheaths Surrounding Electron Emitting Surfaces

A Kinetic Theory of Planar Plasma Sheaths Surrounding Electron Emitting Surfaces A Kinetic Theory of Planar Plasma Sheaths Surrounding Electron Emitting Surfaces J. P. Sheehan1, I. Kaganovich2, E. Barnat3, B. Weatherford3, H. Wang2, 4 1 2 D. Sydorenko, N. Hershkowitz, and Y. Raitses

More information

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

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:

More information

Snakes and similar coherent structures in tokamaks

Snakes and similar coherent structures in tokamaks Snakes and similar coherent structures in tokamaks A. Y. Aydemir 1, K. C. Shaing 2, and F. W. Waelbroeck 1 1 Institute for Fusion Studies, The University of Texas at Austin, Austin, TX 78712 2 Plasma and

More information

Critical Physics Issues for DEMO

Critical Physics Issues for DEMO Max-Planck-Institut für Plasmaphysik Critical Physics Issues for DEMO L.D. Horton with thanks to the contributors to the EFDA DEMO physics tasks in 2006 and to D.J. Campbell, who organized this effort

More information

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

Fast ion physics in the C-2U advanced, beam-driven FRC Fast ion physics in the C-2U advanced, beam-driven FRC Richard Magee for the TAE Team 216 US-Japan Workshop on the Compact Torus August 23, 216! High β FRC embedded in magnetic mirror is a unique fast

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual

More information

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

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OVERVIEW OF THE ALCATOR C-MOD PROGRAM IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OUTLINE C-Mod is compact, high field, high density, high power

More information

Modelling of plasma edge turbulence with neutrals

Modelling of plasma edge turbulence with neutrals Modelling of plasma edge turbulence with neutrals Ben Dudson 1 1 York Plasma Institute, Department of Physics, University of York, Heslington, York YO1 5DD, UK 7 th IAEA TM on Plasma Instabilities 4-6

More information

Theory Work in Support of C-Mod

Theory Work in Support of C-Mod Theory Work in Support of C-Mod 2/23/04 C-Mod PAC Presentation Peter J. Catto for the PSFC theory group MC & LH studies ITB investigations Neutrals & rotation BOUT improvements TORIC ICRF Mode Conversion

More information

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

Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Ghassan Antar Physics Department American University of Beirut http://www.aub.edu.lb/physics/lpfd Outline 1. Introduction and

More information

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

DT Fusion Power Production in ELM-free H-modes in JET JET C(98)69 FG Rimini and e JET Team DT Fusion ower roduction in ELM-free H-modes in JET This document is intended for publication in e open literature. It is made available on e understanding at it may

More information

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

Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants C. E. Kessel 1, M. S. Tillack 2, and J. P. Blanchard 3 1 Princeton Plasma Physics Laboratory 2 University of California, San Diego

More information

Comments About Varied IEC Approaches to Fusion Power

Comments About Varied IEC Approaches to Fusion Power Comments About Varied IEC Approaches to Fusion Power George H Miley NPRE, University of Illinois, Urbana, IL 61801 Email: ghmiley@illinois.edu Abstract IEC Fusion concepts can be broadly categorized as

More information

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

P.Jacquet*, P.Bibet, P.Froissard, G.Rey, F.Surle, M.Tareb. Centre d' 6tudes de Cadarache Association Euratom-CEA The submitted manuscript has been authored by a contractor of the U. S. Government under contractt DE-AC5-96R24464. Accordingly, the U. S. Government retains a non-exclusive, royalty free license to publish

More information

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

Application of atomic data to quantitative analysis of tungsten spectra on EAST tokamak Technical Meeting on Uncertainty Assessment and Benchmark Experiments for Atomic and Molecular Data for Fusion Applications, 19-21 December 2016, Vienna, Austria Application of atomic data to quantitative

More information

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

Time-domain simulation and benchmark of LHCD experiment at ITER relevant parameters Time-domain simulation and benchmark of LHCD experiment at ITER relevant parameters S. Shiraiwa, P. Bonoli, F. Poli 1, R. W, Harvey 2, C. Kessel 1, R. Parker, and G. Wallace MIT-PSFC, PPPL 1, and CompX

More information

Development of LH wave fullwave simulation based on FEM

Development of LH wave fullwave simulation based on FEM Development of LH wave fullwave simulation based on FEM S. Shiraiwa and O. Meneghini on behalf of LHCD group of Alacator C-Mod PSFC, MIT 2010/03/10 San-Diego, CA Special acknowledgements : R. Parker, P.

More information

Neutral beam plasma heating

Neutral beam plasma heating Seminar I b 1 st year, 2 nd cycle program Neutral beam plasma heating Author: Gabrijela Ikovic Advisor: prof.dr. Tomaž Gyergyek Ljubljana, May 2014 Abstract For plasma to be ignited, external heating is

More information

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

Heating and Current Drive by Electron Cyclotron Waves in JT-60U EX/W- Heating and Current Drive by Electron Cyclotron Waves in JT-6U T. Suzuki ), S. Ide ), C. C. Petty ), Y. Ikeda ), K. Kajiwara ), A. Isayama ), K. Hamamatsu ), O. Naito ), M. Seki ), S. Moriyama )

More information

Nuclear Fusion and ITER

Nuclear Fusion and ITER Nuclear Fusion and ITER C. Alejaldre ITER Deputy Director-General Cursos de Verano UPM Julio 2, 2007 1 ITER the way to fusion power ITER ( the way in Latin) is the essential next step in the development

More information

Cosmic Ray Electrons with CTA. R.D. Parsons

Cosmic Ray Electrons with CTA. R.D. Parsons Cosmic Ray Electrons with CTA R.D. Parsons Cosmic Ray Electrons In addi:on to the well known hadronic component of cosmic rays there is a more poorly understood electronic component Has a lower flux than

More information

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

Review of recent experimental and modeling advances in the understanding of lower hybrid current drive in ITER-relevant regimes UKAEA-CCFE-PR(18)32 B. J. Ding, P. T. Bonoli, A. Tuccillo, M. Goniche, K. Kirov, M. Li, Y. Li, R. Cesario, Y. Peysson, A. Ekedahl, L. Amicucci, S. Baek, I. Faust, R. Parker, S. Shiraiwa, G. M. Wallace,

More information

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER

More information

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

Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas P. T. Bonoli*, S. G. Baek, B. LaBombard, K. Filar, M. Greenwald, R. Leccacorvi,

More information

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

Overview Impact of 3D fields (RMP) on edge turbulence and turbulent transport Trilateral Euregio Cluster Overview Impact of 3D fields (RMP) on edge turbulence and turbulent transport TEC Yuhong Xu Laboratory for Plasma Physics, Ecole Royale Militaire - Koninklijke Militaire School,

More information

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

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development

More information

RELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE

RELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE RELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE Abhay K. Ram Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge, MA 02139. U.S.A. Joan Decker

More information

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

INTEGRATED OPERATION OF STEADY-STATE LONG PULSE H-MODE IN EAST Gong et al [Left hand page running head is author s name in Times New Roman 8 point bold capitals, centred. For more than two authors, write AUTHOR et al.] INTEGRATED OPERATION OF STEADY-STATE LONG PULSE

More information

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

Modelling of the EAST lower-hybrid current drive experiment using GENRAY/CQL3D and TORLH/CQL3D Modelling of the EAST lower-hybrid current drive experiment using GENRAY/CQL3D and TORLH/CQL3D The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story

More information

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

Laser- Accelerated Proton Beams and their Medical Applica6ons. By Eric Sacks Laser- Accelerated Proton Beams and their Medical Applica6ons By Eric Sacks Contents 1) Basics of charged par6cle interac6ons in ma@er. 2) Proton- Therapy 3) Laser- Accelera6on method for producing Proton

More information

Disruption mitigation in ITER

Disruption mitigation in ITER Disruption mitigation in ITER S.Putvinski, R.Pitts, M.Sugihara, L.Zakharov Page 1 Outline Introduction Massive gas injection for mitigation of thermal loads Forces on VV and in vessel components Suppression

More information

Additional Heating Experiments of FRC Plasma

Additional Heating Experiments of FRC Plasma Additional Heating Experiments of FRC Plasma S. Okada, T. Asai, F. Kodera, K. Kitano, T. Suzuki, K. Yamanaka, T. Kanki, M. Inomoto, S. Yoshimura, M. Okubo, S. Sugimoto, S. Ohi, S. Goto, Plasma Physics

More information

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

Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor M. Kikuchi, T. Takizuka, S. Medvedev, T. Ando, D. Chen, J.X. Li, M. Austin, O. Sauter, L. Villard, A.

More information

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

Developing Steady State ELM-absent H-Mode scenarios with Advanced Divertor Configuration in EAST tokamak Developing Steady State ELM-absent H-Mode scenarios with Advanced Divertor Configuration in EAST tokamak G. Calabrò, B.J. Xiao, J.G. Li, Z.P. Luo, Q.P. Yuan, L. Wang, K. Wu, R. Albanese, R. Ambrosino,

More information

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

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas 1 EX/P5-4 Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas J.E. Rice 1), A.C. Ince-Cushman 1), P.T. Bonoli 1), M.J. Greenwald 1), J.W. Hughes 1), R.R. Parker 1), M.L. Reinke

More information

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

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control P. A. Politzer, 1 A. W. Hyatt, 1 T. C. Luce, 1 F. W. Perkins, 4 R. Prater, 1 A. D. Turnbull, 1 D. P. Brennan, 5 J.

More information

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

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.

More information

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

C-Mod Advanced Tokamak Program: Recent progress and near-term plans Advanced Tokamak Program: Recent progress and near-term plans Program Advisory Committee Review February 2, 2004 MIT PSFC Presented by A. Hubbard MIT Plasma Science and Fusion Center, for the team Advanced

More information

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

Control of Neo-classical tearing mode (NTM) in advanced scenarios FIRST CHENGDU THEORY FESTIVAL Control of Neo-classical tearing mode (NTM) in advanced scenarios Zheng-Xiong Wang Dalian University of Technology (DLUT) Dalian, China Chengdu, China, 28 Aug, 2018 Outline

More information

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

Impact of H&CD Technology on DEMO Scenario Choice (Impact of DEMO Scenario on Choice of H&CD Technology) Impact of H&CD Technology on DEMO Scenario Choice (Impact of DEMO Scenario on Choice of H&CD Technology) By A.M. Garofalo, R. Prater, V.S. Chan, R.I. Pinsker, G. Staebler, T.S. Taylor, C.P.C. Wong (General

More information

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

Measurement of lower hybrid waves using microwave scattering technique in Alcator C-Mod Measurement of lower hybrid waves using microwave scattering technique in Alcator C-Mod S. Baek, R. Parker, S. Shiraiwa, A. Dominguez, E. Marmar, G. Wallace, G. J. Kramer* Plasma Science and Fusion Center,

More information

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets PFC/JA-91-5 Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets E. A. Chaniotakis L. Bromberg D. R. Cohn April 25, 1991 Plasma Fusion Center Massachusetts Institute of Technology

More information

Concept of Multi-function Fusion Reactor

Concept of Multi-function Fusion Reactor Concept of Multi-function Fusion Reactor Presented by Songtao Wu Institute of Plasma Physics, Chinese Academy of Sciences, P.O. Box 1126, Hefei, Anhui, 230031, P.R. China 1. Motivation 2. MFFR Concept

More information

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

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011 Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor

More information

and expectations for the future

and expectations for the future 39 th Annual Meeting of the FPA 2018 First operation of the Wendelstein 7-X stellarator and expectations for the future Hans-Stephan Bosch Max-Planck-Institut für Plasmaphysik Greifswald, Germany on behalf

More information

ITER A/M/PMI Data Requirements and Management Strategy

ITER A/M/PMI Data Requirements and Management Strategy ITER A/M/PMI Data Requirements and Management Strategy Steven Lisgo, R. Barnsley, D. Campbell, A. Kukushkin, M. Hosokawa, R. A. Pitts, M. Shimada, J. Snipes, A. Winter ITER Organisation with contributions

More information

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

Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER 2267-1 Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics 3-14 October 2011 Introduction to Fusion Leading to ITER SNIPES Joseph Allan Directorate for Plasma Operation Plasma Operations

More information

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

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC Fusion Energy Chijin Xiao and Akira Hirose Plasma Physics laboratory Physics & Engineering Physics University of Saskatchewan Supported by NSERC, CRC Trends in Nuclear & Medical Technologies April il6-7,

More information

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

Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod I.C. Faust, G.M. Wallace, S.G. Baek, D. Brunner, B. LaBombard, R.R. Parker, Y. Lin, S. Shiraiwa, J.L. Terry,

More information

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

Effects of fast ion phase space modifications by instabilities on fast ion modeling Effects of fast ion phase space modifications by instabilities on fast ion modeling M. Podestà, M. Gorelenkova, E. Fredrickson, N. Gorelenkov, R. White PPPL, Princeton USA Acknowledgements: NSTX-U and

More information

Plan of Off-axis Neutral Beam Injector in KSTAR

Plan of Off-axis Neutral Beam Injector in KSTAR KSTAR conference, Feb 25-27, 2015, Daejeon (DCC), Korea Plan of Off-axis Neutral Beam Injector in KSTAR Feb. 26, 2015 DCC, Daejeon, Korea Young-soon Bae a L. Terzolo a, K.S. Lee a, H.K. Kim a, H.L. Yang

More information

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

ENEA for EUROfusion, via E. Fermi 45, Frascati (Rome), Italy 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, , China 3 Quasi-Snowflake divertor studies on EAST G. Calabrò 1, B.J. Xiao 2,3, S. L. Chen 2, Y.M. Duan 2, Y. Guo 2, J.G. Li 2, L. Liu 2, Z.P. Luo 2, L. Wang 2, J. Xu 2, B. Zhang 2, R. Albanese 4, R. Ambrosino 4,

More information

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

RECENT PROGRESSES ON HIGH PERFORMANCE STEADY-STATE PLASMAS IN THE SUPERCONDUCTING TOKAMAK TRIAM-1M RECENT PROGRESSES ON HIGH PERFORMANCE STEADY-STATE PLASMAS IN THE SUPERCONDUCTING TOKAMAK TRIAM-1M Satoshi ITOH, Kohnosuke SATO, Kazuo NAKAMURA, Hideki ZUSHI, Mizuki SAKAMOTO, Kazuaki HANADA, Eriko JOTAKI,

More information

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

Overview of Recent Results from Alcator C-Mod including Applications to ITER Scenarios Overview of Recent Results from Alcator C-Mod including Applications to ITER Scenarios E. S. Marmar and the Alcator C-Mod Team MIT Plasma Science and Fusion Center, Cambridge MA 02139 USA E-mail contact

More information

Focus On : JET Plasma Heating and Current Drive

Focus On : JET Plasma Heating and Current Drive Focus On : JET Plasma Heating and Current Drive Contents: Ohmic Heating Neutral Beam Injection Plasma and electromagnetic waves Ion Cyclotron Resonant Heating Lower Hybrid Current Drive The goal of fusion

More information

Correlations of ELM frequency with pedestal plasma characteristics

Correlations of ELM frequency with pedestal plasma characteristics cpp header will be provided by the publisher Correlations of ELM frequency with pedestal plasma characteristics G. Kamberov 1 and L. Popova 2 1 Stevens Institute of Technology, Hoboken NJ, USA 2 Institute

More information

Chapter IX: Nuclear fusion

Chapter IX: Nuclear fusion Chapter IX: Nuclear fusion 1 Summary 1. General remarks 2. Basic processes 3. Characteristics of fusion 4. Solar fusion 5. Controlled fusion 2 General remarks (1) Maximum of binding energy per nucleon

More information

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

Role of Magnetic Configuration and Heating Power in ITB Formation in JET. Role of Magnetic Configuration and Heating Power in ITB Formation in JET. The JET Team (presented by V. Parail 1 ) JET Joint Undertaking, Abingdon, Oxfordshire, United Kingdom 1 present address: EURATOM/UKAEA

More information

Density Peaking At Low Collisionality on Alcator C-Mod

Density Peaking At Low Collisionality on Alcator C-Mod Density Peaking At Low Collisionality on Alcator C-Mod APS-DPP Meeting Philadelphia, 10/31/2006 M. Greenwald, D. Ernst, A. Hubbard, J.W. Hughes, Y. Lin, J. Terry, S. Wukitch, K. Zhurovich, Alcator Group

More information

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

First Experimental Results with the ITER-Relevant Lower Hybrid Current Drive Launcher in Tore Supra First Experimental Results with the ITER-Relevant Lower Hybrid Current Drive Launcher in Tore Supra EXW/P7-05 A. Ekedahl 1), L. Delpech 1), M. Goniche 1), D. Guilhem 1), J. Hillairet 1), M. Preynas 1),

More information

History of Mechanical Engineering for Fusion Research at Princeton

History of Mechanical Engineering for Fusion Research at Princeton History of Mechanical Engineering for Fusion Research at Princeton ASME Historic Mechanical Engineering Landmark Presenta8on Phil Heitzenroeder and Dale Meade October 5, 2018 Project MaJerhorn/PPL/PPPL

More information

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

Mo#va#on J B = P. Magne&cally confined fusion devices require detailed &meresolved measurement of J(r) and B(r): Mo#va#on Magne&cally confined fusion devices require detailed &meresolved measurement of J(r) and B(r): J B = P Measurements of δβ and δj associated with instabili&es (MHD, fast par&cle modes, turbulence,

More information

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

PIC/MCC Simulation of Radio Frequency Hollow Cathode Discharge in Nitrogen PIC/MCC Simulation of Radio Frequency Hollow Cathode Discharge in Nitrogen HAN Qing ( ), WANG Jing ( ), ZHANG Lianzhu ( ) College of Physics Science and Information Engineering, Hebei Normal University,

More information

MHD. Jeff Freidberg MIT

MHD. Jeff Freidberg MIT MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium

More information

ICRH Experiments on the Spherical Tokamak Globus-M

ICRH Experiments on the Spherical Tokamak Globus-M 1 Experiments on the Spherical Tokamak Globus-M V.K.Gusev 1), F.V.Chernyshev 1), V.V.Dyachenko 1), Yu.V.Petrov 1), N.V.Sakharov 1), O.N.Shcherbinin 1), V.L.Vdovin 2) 1) A.F.Ioffe Physico-Technical Institute,

More information

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

Progress in understanding W control using ICRH in the JET-ILW tokamak Progress in understanding W control using ICRH in the JET-ILW tokamak P.Mantica 20 th US-EU TTF Workshop, Salem, MA, US 28 th April-1 st May 2015 Acknowledgements P.Mantica1, C.Angioni2, R.Bilato2, F.Casson3,

More information

Progress Toward High Performance Steady-State Operation in DIII D

Progress Toward High Performance Steady-State Operation in DIII D Progress Toward High Performance Steady-State Operation in DIII D by C.M. Greenfield 1 for M. Murakami, 2 A.M. Garofalo, 3 J.R. Ferron, 1 T.C. Luce, 1 M.R. Wade, 1 E.J. Doyle, 4 T.A. Casper, 5 R.J. Jayakumar,

More information

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

Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas Nathan Howard 1 with C. Holland 2, A.E. White 1, M. Greenwald 1, J. Candy 3, P. Rodriguez- Fernandez 1, and

More information

Analysis of Ion Cyclotron Heating Issues for ITER

Analysis of Ion Cyclotron Heating Issues for ITER 1 TH/P6-8 Analysis of Ion Cyclotron Heating Issues for ITER L.A. Berry 1), D.B. Batchelor 1), P.T. Bonoli 2), M.D. Carter 1), M. Choi 3), W.A. Houlberg 1), D.A. D Ippolito 4), R.W. Harvey 5), E.F. Jaeger

More information

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

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads Mitglied der Helmholtz-Gemeinschaft Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads J. Linke, J. Du, N. Lemahieu, Th. Loewenhoff, G. Pintsuk, B. Spilker, T. Weber,

More information