11 Association Euratom-Cea The PION code L.-G. Eriksson Association EURATOM-CEA, CEA/DSM/IRFM, CEA-Cadarache, St. Paul lez Durance, France T. Hellsten.

Slides:



Advertisements
Similar presentations
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
Advertisements

Electron Acceleration in the Van Allen Radiation Belts by Fast Magnetosonic Waves Richard B. Horne 1 R. M. Thorne 2, S. A. Glauert 1, N. P. Meredith 1.
1 Association Euratom-CEA TORE SUPRA EAST, China 7 th Jan 2010 X.L. Zou Observation of Strong Inward Heat Transport In Tore Supra with Off-Axis ECRH S.D.
Effect of supra thermal electrons on particle charge in RF sheath A.A.Samarian and S.V. Vladimirov School of Physics, University of Sydney, NSW 2006, Australia.
Modeling Generation and Nonlinear Evolution of Plasma Turbulence for Radiation Belt Remediation Center for Space Science & Engineering Research Virginia.
METO 621 Lesson 5. Natural broadening The line width (full width at half maximum) of the Lorentz profile is the damping parameter, . For an isolated.
Physics of fusion power Lecture 14: Collisions / Transport.
Finite Temperature Effects on VLF-Induced Precipitation Praj Kulkarni, U.S. Inan and T. F. Bell MURI Review February 18, 2009.
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.
Physics of fusion power
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
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 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.
Modelling of the Effects of Return Current in Flares Michal Varady 1,2 1 Astronomical Institute of the Academy of Sciences of the Czech Republic 2 J.E.
Microstability analysis of e-ITBs in high density FTU plasmas 1)Associazione EURATOM-ENEA sulla fusione, C.R. Frascati, C.P , Frascati, Italy.
Introduction to the Particle In Cell Scheme for Gyrokinetic Plasma Simulation in Tokamak a Korea National Fusion Research Institute b Courant Institute,
Particle Distribution Modification by TAE mode and Resonant Particle Orbits POSTECH 1, NFRI 1,2 M.H.Woo 1, C.M.Ryu 1, T.N.Rhee 1,,2.
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
Initial Exploration of HHFW Current Drive on NSTX J. Hosea, M. Bell, S. Bernabei, S. Kaye, B. LeBlanc, J. Menard, M. Ono C.K. Phillips, A. Rosenberg, J.R.
D. A. Gates, R. B. White NSTX Physics Meeting 1/19/03
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,
Laser Energy Transport and Deposition Package for CRASH Fall 2011 Review Ben Torralva.
1 ITPA St Petersburg April 2009G.Gorini JET results on the determination of thermal/non-thermal fusion yield from neutron emission spectroscopy.
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.
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
The propagation of a microwave in an atmospheric pressure plasma layer: 1 and 2 dimensional numerical solutions Conference on Computation Physics-2006.
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
RF codes for Transp Transp User Course 2014 Jim Conboy.
1 Confinement Studies on TJ-II Stellarator with OH Induced Current F. Castejón, D. López-Bruna, T. Estrada, J. Romero and E. Ascasíbar Laboratorio Nacional.
Libor Novák. The Coulomb potential which the particles have to overcome in order to fuse is given by: This relation can be applied at distances greater.
INFSO-RI Enabling Grids for E-sciencE Workflows in Fusion applications José Luis Vázquez-Poletti Universidad.
Excitation of internal kink mode by barely trapped suprathermal electrons* Youwen Sun, Baonian Wan, Shaojie Wang, Deng Zhou, Liqun Hu and Biao Shen * Sun.
(National Institute for Fusion Science, Japan)
SLM 2/29/2000 WAH 13 Mar NBI Driven Neoclassical Effects W. A. Houlberg ORNL K.C. Shaing, J.D. Callen U. Wis-Madison NSTX Meeting 25 March 2002.
Beam Voltage Threshold for Excitation of Compressional Alfvén Modes E D Fredrickson, J Menard, N Gorelenkov, S Kubota*, D Smith Princeton Plasma Physics.
Parallel coupling: problems arising in the context of magnetic fusion John R. Cary Professor, University of Colorado CEO, Tech-X Corporation.
Magnetic Reconnection in Plasmas; a Celestial Phenomenon in the Laboratory J Egedal, W Fox, N Katz, A Le, M Porkolab, MIT, PSFC, Cambridge, MA.
Non-linear MHD modelling of RMPs with toroidal rotation and resonant and non-resonant plasma braking. M.Becoulet G. Huysmans, E. Nardon Association Euratom-CEA,
Characterization of Fast Ion Power Absorption of HHFW in NSTX A. Rosenberg, J. Menard, J.R. Wilson, S. Medley, R. Dumont, B.P. LeBlanc, C.K. Phillips,
A.Yu. Chirkov1), S.V. Ryzhkov1), P.A. Bagryansky2), A.V. Anikeev2)
52nd Annual Meeting of the Division of Plasma Physics, November , 2010, Chicago, Illinois Non-symmetric components were intentionally added to the.
T. Hellsten IAEA TM Meeting on Energetic Particles, San Diego 2003 T. Hellsten 1, T. Bergkvist 1, T.Johnson 1, M. Laxåback 1 and L.-G. Eriksson 2 1 Euratom-VR.
53rd Annual Meeting of the Division of Plasma Physics, November , 2011, Salt Lake City, Utah When the total flow will move approximately along the.
Presented by Yuji NAKAMURA at US-Japan JIFT Workshop “Theory-Based Modeling and Integrated Simulation of Burning Plasmas” and 21COE Workshop “Plasma Theory”
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
1 Laboratório Associado de Plasma, Instituto Nacional de Pesquisas Espaciais São José dos Campos, SP, Brazil Fluid model of electron cyclotron.
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.
TH/7-1Multi-phase Simulation of Alfvén Eigenmodes and Fast Ion Distribution Flattening in DIII-D Experiment Y. Todo (NIFS, SOKENDAI) M. A. Van Zeeland.
TEC Short introduction to plasma fluid theory Dominik Schega.
Hard X-rays from Superthermal Electrons in the HSX Stellarator Preliminary Examination for Ali E. Abdou Student at the Department of Engineering Physics.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
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.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
A Global Hybrid Simulation Study of the Solar Wind Interaction with the Moon David Schriver ESS 265 – June 2, 2005.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Saturation Roi Levy. Motivation To show the deference between linear and non linear spectroscopy To understand how saturation spectroscopy is been applied.
Mechanisms for losses during Edge Localised modes (ELMs)
Enhancement of Wind Stress and Hurricane Waves Simulation
Chapter 3 Plasma as fluids
Kinetic Theory.
Studies of Bias Induced Plasma Flows in HSX
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
20th IAEA Fusion Energy Conference,
V. Rozhansky1, E. Kaveeva1, I. Veselova1, S. Voskoboynikov1, D
Electron Acoustic Waves (EAW) EAW’s are novel kinetic waves that exist only because nonlinear trapping turns off Landau damping. We recently provided.
Presentation transcript:

11 Association Euratom-Cea The PION code L.-G. Eriksson Association EURATOM-CEA, CEA/DSM/IRFM, CEA-Cadarache, St. Paul lez Durance, France T. Hellsten 2 Association Euratom-VR, KTH, Stockholm, Sweden

22 Association Euratom-Cea Outline Introduction Power deposition model Fokker-Planck model Modified dielectric tensor due to non- thermal ions Experimental validation Conclusions

33 Association Euratom-Cea Introduction In the late eighties at JET quantities directly affected by ICRF heated fast ions began to be measured routinely (non-thermal neutron rates, fast ion energy contents etc.) The experimentalists started to ask why the useless theory types, in spite of their fancy codes, could not model the measured quantities. It was quite clear that with the computers 15 years ago it would be very challenging combine a full wave code even with 2D Fokker-Planck code. We therefore started to develop simplified modelling that, as we see it, contains the most essential elements. The result was the PION * code. PION is run routinely in CHAIN2 at JET * L.-G. Eriksson, T. Hellsten and U. Willén, Nucl. Fusion 33 (1993) 1037.

44 Association Euratom-Cea Power deposition model The power deposition model was developed by Hellsten and Villard * It is based on a fundamental observation of the behaviour of wave fields in a Tokmak T. Hellsten and L. Villard, Nuclear Fusion 28, 285 (1998).

55 Association Euratom-Cea Wave fields for strong & weak damping Strong damping, focussing of the wave at first passage. Weak damping, the wave field fills much of the cavity; JET, (H)D n H /n D ~ 5%. T ||H = 20keV N  =25 ERER ERER JET, ( 3 He)D n He /n D ~5%. T ||He = 5keV N  =25 LION code * * L. Villard et al., Computer Physics Reports 4, 95 (1986).

66 Association Euratom-Cea Strong Weak Total absorbed power Power deposition controlled by Doppler broadening of the cyclotron resonance ( ) Power deposition determined by wave field distribution and the absorption strength along the cyclotron resonance and

77 Association Euratom-Cea In a case with medium strong absorption, there will be a mix of the two fundamental cases. From the power deposition point of view, two quantities are important to estimate well: –The averaged square parallel velocity of the resonating ion species. –The damping strength of the different species. Both depend on the distribution function of the resonating species. It is important to have a consistency between the power deposition and Fokker-Planck calculations.

88 Association Euratom-Cea Ansatz for the flux surface averaged Poynting flux (or power absorbed within a flux surface). Represents limit of strong damping. Represents limit of weak damping. Flux surface averaged power density a s is the single pass absorption coefficient calculated in the mid-plane

99 Association Euratom-Cea The strong damping, P S (s), can easily be computed by a simple ray-tracing (now used instead of model 1 ). Ansatz: Central resonance Off-axis, mid radius resonance g(s) was obtained by averaging power depositions in the weak limit, calculated by the LION code, over small changes in toroidal mode numbers and densities. ; 1 T. Hellsten and L. Villard, Nuclear Fusion 28, 285 (1998).

10 Association Euratom-Cea Examples of comparison between the model and the LION code. (H)D, strong damping ( 3 He)D, weak damping (H)D, off axis resonance

11 Association Euratom-Cea Fokker-Planck model The problem when one starts to do modelling on real experiments is that the power densities normally are very high, several MW/m 3 are typical in e.g. JET. Fast ions in the multi MeV range are therefore created. The 2D Fokker-Planck codes available at JET at the time (late eighties) could cope with MW/m 3. We therefore decided to go for a simplified 1D Fokker-Planck model.

12 Association Euratom-Cea In PION a 1D Fokker-Planck equation equation for the pitch angle averaged distribution function, (  = v ||0 /v ) is solved: A finite difference scheme with adaptive time step and grid is used to solve the 1D Fokker-Planck equation.

13 Association Euratom-Cea Approximate form of the RF operator Is normalised to give the power density obtained from the power deposition code.

14 Association Euratom-Cea From the solution of the Fokker-Planck equation we can easily calculate the following quantities.,, Where – +/-/c denotes powers absorbed due o the |E + | 2 / |E - | 2 /2Re(E + E - * ) components of the electric field; –M denotes the absorption by a equivalent Maxwellian

15 Association Euratom-Cea The averaged parallel velocity of a species at the cyclotron resonance is estimated with a formula, The physics basis is that the strength of the pitch angle scattering ~ (v  / v ) 3.  0 =  0R

16 Association Euratom-Cea It soon became obvious that the orbit width of typical ICRF heated ions can be very large in machines like JET. The resonating ions tend to be trapped and pile up with their turning points close to the exact cyclotron resonance.  = n  ci The collision coefficients at non-thermal energies are therefore averaged over orbits of trapped particles with turning points close to the resonance. The fast ion pressure profile, the profiles of collisional power transfer etc. are re-distributed over the same orbits.

17 Association Euratom-Cea Influence of the distribution function on the power deposition The absorbed power density can be written as Using the gamma factors discussed earlier we calculate the anti-Hermitian parts of the dielectric tensor.

18 Association Euratom-Cea We have for a general distribution function: Three equations  we can solve for the three unknowns: By using Kramers Kronig’s relations we can also calculate approximate expressions for the Hermitian parts of the dielectric tensor

19 Association Euratom-Cea Flow chart: call to PION Start First call to PION? Initialisations; f j,res, set to Maxwellian(s); T || j =T i,  + j =1,  - j =1,  c j =1 Read background plasma parameters yes no Power deposition with T || j and modified with the factors  + j,  - j and  c j  p j (s), E - /E +, k  Fokker-Planck calculation to advance f j,res, a time step to t n+1 = t n +  t  T || j,  + j,  - j,  c j, p ce (s), p ci (s) Return

20 Association Euratom-Cea D. Start, D. Start et al., Nuclear Fusion 39, 321 (1999); * L.-G. Eriksson, M. Mantsinen et al., Nuclear Fusion 39, 337 (1999). Analysis of JET discharges (D)T Q IN = 0.22 Modelling in good agreement with experiment.

21 Association Euratom-Cea Finite orbit width (FOW) effects The first version of PION did not include FOW. The figure shows a comparison with experimental results with and without modelling of FOB in PION. Conclusion: if you want to do serious modelling of ICRF heated JET plasma don’t even think about leaving out finite orbit width effects. #12298; n e0 = 3.6 x 10 l9 m -3 T e = 7.0; P ICRF =8.0 MW. H(D) Without With FOB

22 Association Euratom-Cea Conclusion The PION approach includes the most important effects of ICRF heating in a simplified way. The results obtained tend to be robust. PION has been extensively benchmarked against JET results. Obviously, the PION approach has many limitations, e.g. cases with directed wave spectra and strong ICRF induced spatial transport cannot be handled. For detailed studies of ICRF physics a more comprehensive approach is needed.

23 Association Euratom-Cea Second harmonic T heating in DT PION simulation; n He-3 = 0