Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 8. Heating and current drive Neutral beam heating and current drive,... to be continued.

Slides:



Advertisements
Similar presentations
Presentation on RF Heating by - Saurabh Kumar Vij
Advertisements

H-mode characterization for dominant ECR heating and comparison to dominant NBI or ICR heating F. Sommer PhD thesis advisor: Dr. Jörg Stober Academic advisor:
CHAPTER 3 MICROWAVE ‘O’ TYPE TUBES
Active Control of MHD Stability, Austin, 3-5 November 2003J.A. Hoekzema, FZ-Juelich / IPP Association EURATOM-FOM FOM-Instituut voor Plasmafysica “Rijnhuizen”
PH0101 Unit 2 Lecture 4 Wave guide Basic features
Cyclic MHD Instabilities Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Seminar talk at the ‚Advanced Course‘ of EU PhD Network, Garching, September.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
Chapter 4 Waves in Plasmas 4.1 Representation of Waves 4.2 Group velocity 4.3 Plasma Oscillations 4.4 Electron Plasma Waves 4.5 Sound Waves 4.6 Ion Waves.
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
Modeling Generation and Nonlinear Evolution of VLF Waves for Space Applications W.A. Scales Center of Space Science and Engineering Research Virginia Tech.
ECE 4321 Computer Networks Chapter 4 Transmission Media: Wireless.
Whistler Wave Launch and Diamagnetic Plasma Formation in Laboratory Experiments Bill H. Quon, Microwave Plasma Applications 252 S. Poplar Ave # 403 Brea,
Physics of fusion power Lecture 10 : Running a discharge / diagnostics.
IAEA 2004 ICRH 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.
5. Simplified Transport Equations We want to derive two fundamental transport properties, diffusion and viscosity. Unable to handle the 13-moment system.
PARS Workshop on Novel Methods of Excitation of ULF/ELF/VLF to Improve Efficiency and Availability" November 3 - 6, 2002 Sponsored by Air Force Research.
By C. P. Moeller General Atomics, San Diego, California , USA RF Launchers That Survive Presented at the Renew theme III workshop at UCLA, March.
1 Electron Bernstein Wave Research and Plans Gary Taylor Presentation to the 16th NSTX Program Advisory Committee September 9, 2004.
T. Hellsten IEA Burning Plasma Workshop, July 2005 Tarragona Spain Integrated Modelling of ICRH and AE Dynamics T. Hellsten, T. Bergkvist, T. Johnson and.
1 ST workshop 2008 Conception of LHCD Experiments on the Spherical Tokamak Globus-M O.N. Shcherbinin, V.V. Dyachenko, M.A. Irzak, S.A. Khitrov A.F.Ioffe.
Parallel and Poloidal Sheared Flows close to Instability Threshold in the TJ-II Stellarator M. A. Pedrosa, C. Hidalgo, B. Gonçalves*, E. Ascasibar, T.
1 ST workshop 2005 Numerical modeling and experimental study of ICR heating in the spherical tokamak Globus-M O.N.Shcherbinin, F.V.Chernyshev, V.V.Dyachenko,
1 Association Euratom-Cea TORE SUPRA Tore Supra “Fast Particles” Experiments LH SOL Generated Fast Particles Meeting Association Euratom IPP.CR, Prague.
IPP - Garching Reflectometry Diagnostics and Rational Surface Localization with Fast Swept Systems José Vicente
PROGRESS IN IN THE PROJECT OF THE HIGH FIELD SIDE REFLECTOMETRY SYSTEM FOR THE MAIN PLASMA IN ITER V. A. Vershkov, D. A. Shelukhin, A. O. Urazbaev,
The principle of SAMI and some results in MAST 1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, , China 2. Culham Centre.
Jmn Physics of RF Heating J.-M. Noterdaeme with the support of M. Brambilla, R. Bilato, D. Hartmann, H. Laqua, F. Leuterer, M. Mantsinen, F. Volpe,
PLASMA HEATING AND HOT ION SUSTAINING IN MIRROR BASED HYBRIDS
RADIO-FREQUENCY HEATING IN STRAIGHT FIELD LINE MIRROR NEUTRON SOURCE V.E.Moiseenko 1,2, O.Ågren 2, K.Noack 2 1 Kharkiv Institute of Physics and Technology,
10th ITPA conference, Avila, 7-10 Jan Effects of High Energy Ions Accelerated in front of ICRF Antennas in LHD S. Masuzaki on behalf of the LHD Experimental.
Current Drive for FIRE AT-Mode T.K. Mau University of California, San Diego Workshop on Physics Issues for FIRE May 1-3, 2000 Princeton Plasma Physics.
Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 5. Electromagnetic radiation from tokamaks Introduction, EM waves, cyclotron radiation, bremsstrahlung,
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
Travelling Wave Tube For Broadband amplifier helix TWTs (proposed by Pierce and others in 1946 ) are widely used For High average power purposes the.
4. Mg islands, electric fields, plasma rotation
RF codes for Transp Transp User Course 2014 Jim Conboy.
1 KIT – Universität des Landes Baden-Württemberg und nationales Forschungszentrum in der Helmholtz-Gemeinschaft Institute for Pulsed Power.
Advances In High Harmonic Fast Wave Heating of NSTX H-mode Plasmas P. M. Ryan, J-W Ahn, G. Chen, D. L. Green, E. F. Jaeger, R. Maingi, J. B. Wilgen - Oak.
Yi HUANG Department of Electrical Engineering & Electronics
A Microwave Reflectometry Based On Amplitude Modulation onHT-7 Tokamak B.L.Ling, Institute of Plasma Physics, Chinese Academy of Sciences, P.O.Box 1126,
Emanuele Poli, 17 th Joint Workshop on ECE and ECRH Deurne, May 7-10, 2012 Assessment of ECCD-Assisted Operation in DEMO Emanuele Poli 1, Emiliano Fable.
D. Tskhakaya, LH SOL Generated Fast Particles Meeting IPP.CR, Prague December 16-17, 2004 Quasi-PIC modelling of electron acceleration in front of the.
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
HL-2A Heating & Current Driving by LHW and ECW study on HL-2A Bai Xingyu, HL-2A heating team.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
1 LHCD Properties with a New Lower Hybrid Wave Antenna on HT-7 Tokamak Wei Wei,Guangli Kuang,Bojiang Ding,Weici Shen and HT-7 Team Institute of Plasma.
Summary of RF-Related Presentations at the 2011 EPS Meeting G. Taylor NSTX Physics Meeting July 25, 2011 NSTX Supported by 1.
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Taming The Physics For Commercial Fusion Power Plants ARIES Team Meeting.
Active Control of Neoclassical Tearing Modes toward Stationary High-Beta Plasmas in JT-60U A. Isayama 1), N. Oyama 1), H. Urano 1), T. Suzuki 1), M. Takechi.
47th Annual Meeting of the Division of Plasma Physics, October 24-28, 2005, Denver, Colorado ECE spectrum of HSX plasma at 0.5 T K.M.Likin, H.J.Lu, D.T.Anderson,
1 NSTX EXPERIMENTAL PROPOSAL - OP-XP-712 Title: HHFW Power Balance Optimization at High B Field J. Hosea, R. Bell, S. Bernabei, L. Delgado-Aparicio, S.
5.4 Stored Energy Crashes  Diamagnetic loop shows the plasma energy crashes at low plasma density  ECE signals are in phase with the energy crashes 
Presented by Gary Taylor In collaboration with Cynthia Phillips, Phil Ryan, Randy Wilson and The NSTX RF Research Team NSTX Wave-Particle Physics, Heating.
Nonlinear plasma-wave interactions in ion cyclotron range of frequency N Xiang, C. Y Gan, J. L. Chen, D. Zhou Institute of plasma phsycis, CAS, Hefei J.
1 E. Kolemen / IAEA / October 2012 Egemen Kolemen 1, A.S. Welander 2, R.J. La Haye 2, N.W. Eidietis 2, D.A. Humphreys 2, J. Lohr 2, V. Noraky 2, B.G. Penaflor.
6 th ITPA MHD Topical Group Meeting combined with W60 IEA Workshop on Burning Plasmas Summary Session II MHD Stability and Fast Particle Confinement chaired.
= 2·10 18 m -3 T e (0) = 0.4 keV ECH and ECE on HSX Stellarator K.M.Likin, A.F.Almagri, D.T.Anderson, F.S.B.Anderson, C.Deng 1, C.W.Domier 2, R.W.Harvey.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
54 th APS-DPP Annual Meeting, October 29 - November 2, 2012, Providence, RI Study of ICRH and Ion Confinement in the HSX Stellarator K. M. Likin, S. Murakami.
New prototype modulator for the European XFEL Project (DESY) Pulse Step Modulator (PSM) Technology for long pulse applications.
Waves in magnetized plasma
Study on Electron Cyclotron Heating (ECH)
C.K. Phillips, J. Hosea, E. Valeo, J.R. Wilson PPPL
ESS 154/200C Lecture 19 Waves in Plasmas 2
First Experiments Testing the Working Hypothesis in HSX:
Influence of energetic ions on neoclassical tearing modes
Ioffe Summary Fast MHD oscillations observed on the TUMAN-3M in absence of energetic ions Bursts of the oscillations correlate with saw-tooth crashes and.
PH0101 Unit 2 Lecture 4 Wave guide Basic features
Presentation transcript:

Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 8. Heating and current drive Neutral beam heating and current drive,... to be continued

Neutral Beam Injection: principle Ion source Neutral beam Electricity -> other form (kinetic energy of particles) Transport to plasma (outside part) Neutraliser Magnetic filter Beam duct (inside part) Accellerator IonisationThermalisation

NBI Principle, in more detail I E Day

Size matters – ITER beamline vs Torus I E Day

Evolution from Present Status - ITER

Tokamak Physics6 Neutral beam heating 8: Heating and current drive =

Tokamak Physics7 Neutral beam heating 8: Heating and current drive

Tokamak Physics8 Neutral beam heating 8: Heating and current drive

Tokamak Physics9 Beam slowing 8: Heating and current drive

Tokamak Physics10 Distribution function 8: Heating and current drive

Tokamak Physics11 Beam current drive 8: Heating and current drive

Wave heating Electricity -> other form (electromagnetic oscillations) Transport to plasma (outside part) transmission lines antenna (inside part) waves Thermalisation Antenna Wave to particles Resonance zone R

Classification of waves phase velocity –fast –slow direction of propagation –k parallel to B 0 : according to polarisation (with respect to B 0, in other fields of science –e.g. optics- wrt propagation direction) right -> direction of rotation of electrons left -> direction of rotation of ions –k perpendicular to B 0 ordinary: E 1 // B 0 extraordinary: E 1 perp to B 0

Tokamak Physics14 Wave Heating 8: Heating and current drive Review of Plasma Waves

Tokamak Physics15 Wave Heating 8: Heating and current drive Dielectric Tensor

Tokamak Physics16 Wave Heating 8: Heating and current drive Classification of waves

Tokamak Physics17 Wave Heating 8: Heating and current drive Resonances, Cut-offs

Tokamak Physics18 Wave Heating 8: Heating and current drive Resonances, Cut-offs

Tokamak Physics19 Wave Heating 8: Heating and current drive Energy flow

Tokamak Physics20 Wave Heating: Ray tracing 8: Heating and current drive

Tokamak Physics21 Wave Heating: Ray tracing 8: Heating and current drive ASDEX-U

Tokamak Physics22 Wave Heating: Ray tracing 8: Heating and current drive Mode conversion Boundary conditions

Tokamak Physics23 Wave Heating: CMA diagram 8: Heating and current drive In each region, the topological form of the phase velocity remain unchanged. Fast wave is outside (the wave front in vacuum which would always be a circle) slow wave is inside. E.g. in the top left region (high B, low n) the X/L wave is slow, the O/R wave is fast (X and O have k || B, L and R have k ┴ B)

Tokamak Physics24 Ion Cyclotron Heating 8: Heating and current drive fast wave~ tens of MHz Plasma edge cutoff below heating on harmonic frequencies on minorities (e.g. on H in D plasmas) Resonant layer is vertical at Heating on harmonics  energies often higher than E c  relaxation is mostly due to heating of electrons

Tokamak Physics25 Ion Cyclotron Heating 8: Heating and current drive

Tokamak Physics26 Ion Cyclotron Heating 8: Heating and current drive Heating on minorities: Decreases with increasing concentration, however, new “ion-ion” hybrid resonance emerges. May result in IBW (Ion Bernstein Wave)  can drive electrons Disadvantage: strongly sensitive on minority concentration ICRH advantages: Economic, powerful, important ion heating disadvantages: high E, problems with reflected power (ELMs), (“coupling of waves to plasma”, in particular problems with ELMs), non-directional.

Plasma edge – evanescent region (cutoff below ) i.e. “waves tunnels through” The antenna produces a wide spectrum  wide spectrum of fast electrons due to the Landau damping  current drive Tokamak Physics27 Lower Hybrid Resonance 8: Heating and current drive Slow wave at a small angle to B ~ GHz  long path to the resonant region  Landau damping along the path turns out to be more important than LH itself Reminder: The current drive would not exist if distribution of velocities of plasma particles were flat. However, Maxwellian distribution is not flat, which means wave can locally flatten the distribution in the direction of the wave propagation.

Tokamak Physics28 Lower Hybrid Resonance 8: Heating and current drive

Mode converter Equally split the RF power in 3 in the poloidal direction 1 input & 3 outputs WR-229 Conversion efficiency: % Return Loss: -20.5dB J. Hilairet

LH - Wave Propagation Depends on n e and B Antenna structure

Tokamak Physics31 Electron Cyclotron Resonance 8: Heating and current drive Advantages : no evanescent region highly directional highest achievable power density Disadvantages:acts only on electrons expensive new technology (less reliable) Highly directional  profile control e.g. suppression of NTMs (mg. islands)

Tokamak Physics32 Electron Cyclotron Resonance 8: Heating and current drive

Tokamak Physics33 Electron Cyclotron Resonance 8: Heating and current drive

Tokamak Physics34 Electron Cyclotron Resonance 8: Heating and current drive Current Drive (ECCD) Other applications of ECR: 1)Fisch – Boozer directional increase of decreases 2)Ohkawa increase of pushes passing particles into the trapped region (opposite direction to the Fisch - Boozer)  lower momentum loss - plasma heating - current profile control for advanced regimes - transport studies via modulated ECRH - plasma start-up assistance - wall conditioning (ITER)

Tokamak Physics35 Bulk and Tail Current Drive 8: Heating and current drive

Tokamak Physics36 ITER ECR system 8: Heating and current drive 24 x 1 MW, 170 GHz gyrotrons 3 x 1 MW, 120 GHz gyrotrons for SUA wave guide switch to … equatorial or upper launcher

Tokamak Physics37 ITER ECR Upper Port 8: Heating and current drive 3 ports with 8 beams in two rows Main function: NTM (and sawtooth) control Front steering –In vertical direction to scan radial deposition –Well focussed for optimised localization at q=3/2 and 2