DIII-D 3D edge physics capabilities: modeling, experiments and physics validation Presented by T.E. Evans 1 I. Joseph 2, R.A. Moyer 2, M.J. Schaffer 1,

Slides:



Advertisements
Similar presentations
Dynamo Effects in Laboratory Plasmas S.C. Prager University of Wisconsin October, 2003.
Advertisements

Magnetic Relaxation in MST S. Prager University of Wisconsin and CMSO.
Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Progress and Plans on Magnetic Reconnection for CMSO For NSF Site-Visit for CMSO May1-2, Experimental progress [M. Yamada] -Findings on two-fluid.
Barbora Gulejová 1 of 12 Centre de Recherches en Physique des Plasmas SPS Annual Meeting in Lausanne, 14/2/2006 SOLPS5 modelling of ELMing H-mode on TCV.
6th Japan Korea workshop July 2011, NIFS, Toki-city Japan Edge impurity transport study in stochastic layer of LHD and scrape-off layer of HL-2A.
A. Kirk, 21 st IAEA Fusion Energy Conference, Chengdu, China, October 2006 Evolution of the pedestal on MAST and the implications for ELM power loadings.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
Toroidally resolved measurements of ELMs in RMP and non-RMP H-mode discharges on DIII-D M.W. Jakubowski 1, T.E. Evans 3, C.J. Lasnier 4, O. Schmitz 2,
Cyclic MHD Instabilities Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Seminar talk at the ‚Advanced Course‘ of EU PhD Network, Garching, September.
Nonlinear Simulations of ELMs with NIMROD D.P. Brennan Massachussetts Institute of Technology Cambridge, MA S.E. Kruger Tech-X Corp, Boulder, CO A. Pankin,
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
Modeling of ELM Dynamics for ITER A.Y. PANKIN 1, G. BATEMAN 1, D.P. BRENNAN 2, A.H. KRITZ 1, S. KRUGER 3, P.B. SNYDER 4, and the NIMROD team 1 Lehigh University,
Chalmers University of Technology The L-H transition on EAST Jan Weiland and C.S. Liu Chalmers University of Technoloy and EURATOM_VR Association, S
M.E. Fenstermacher - Summary of Progress and Outlook for Work Plan in PEP ITPA WG on RMP ELM Control 4/23/09 11:15 PM 1 PEP ITPA Working Group on RMP ELM.
pkm- NCSX CDR, 5/21-23/ Power and Particle Handling in NCSX Peter Mioduszewski 1 for the NCSX Boundary Group: for the NCSX Boundary Group: M. Fenstermacher.
SIMULATION OF A HIGH-  DISRUPTION IN DIII-D SHOT #87009 S. E. Kruger and D. D. Schnack Science Applications International Corp. San Diego, CA USA.
6 th Japan-Korea Workshop on Theory and Simulation of Magnetic Fusion Plasmas Hyunsun Han, G. Park, Sumin Yi, and J.Y. Kim 3D MHD SIMULATIONS.
Model prediction of impurity retention in ergodic layer and comparison with edge carbon emission in LHD (Impurity retention in the ergodic layer of LHD)
Overview of MHD and extended MHD simulations of fusion plasmas Guo-Yong Fu Princeton Plasma Physics Laboratory Princeton, New Jersey, USA Workshop on ITER.
Challenging problems in kinetic simulation of turbulence and transport in tokamaks Yang Chen Center for Integrated Plasma Studies University of Colorado.
Plasma Dynamics Lab HIBP E ~ 0 V/m in Locked Discharges Average potential ~ 580 V  ~ V less than in standard rotating plasmas Drop in potential.
Rotation effects in MGI rapid shutdown simulations V.A. Izzo, P.B. Parks, D. Shiraki, N. Eidietis, E. Hollmann, N. Commaux TSD Workshop 2015 Princeton,
M.E. Fenstermacher - Status of Progress on Work Plan in PEP ITPA WG on RMP ELM Control 12/5/07 11:15 PM 1 PEP ITPA Working Group on RMP ELM Control: 1.
G.HuysmansETFP2006, Krakow11-13/9/2006 Edge Localised Modes: Theory/Simulation Guido Huysmans Association Euratom-CEA Cadarache, France ETFP2006, Krakow.
G.Huysmansworkshop : Principles of MHD 21-24/3/2005 MHD in Tokamak Plasmas Guido Huysmans Association Euratom/CEA Cadarache, France with contributions.
Global Stability Issues for a Next Step Burning Plasma Experiment UFA Burning Plasma Workshop Austin, Texas December 11, 2000 S. C. Jardin with input from.
14 Oct. 2009, S. Masuzaki 1/18 Edge Heat Transport in the Helical Divertor Configuration in LHD S. Masuzaki, M. Kobayashi, T. Murase, T. Morisaki, N. Ohyabu,
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
NSTX APS DPP 2008 – RWM Stabilization in NSTX (Berkery)November 19, Resistive Wall Mode stabilization in NSTX may be explained by kinetic theory.
Tech-X Corporation1 Boundary Conditions In the NIMROD Code S.E. Kruger Tech-X Corporation D.D. Schnack U.W. - Madison.
Plasma-wall interactions during high density operation in LHD
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
EXTENSIONS OF NEOCLASSICAL ROTATION THEORY & COMPARISON WITH EXPERIMENT W.M. Stacey 1 & C. Bae, Georgia Tech Wayne Solomon, Princeton TTF2013, Santa Rosa,
TEC Trilateral Euregio Cluster Institut für PlasmaphysikAssoziation EURATOM-Forschungszentrum Jülich 21st IAEA Fusion Energy Conference, October.
1 A Proposal for a SWIM Slow-MHD 3D Coupled Calculation of the Sawtooth Cycle in the Presence of Energetic Particles Josh Breslau Guo-Yong Fu S. C. Jardin.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
NIMROD Simulations of a DIII-D Plasma Disruption
Physics Analysis and Flexibility Issues for FIRE NSO PAC-2 Meeting January 17-18, 2001 S. C. Jardin with input from C.Kessel, J.Mandrekas, D.Meade, and.
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
Dependence of Pedestal Structure on Ip and Bt A. Diallo, R. Maingi, S. Zweben, B.P. LeBlanc, B. Stratton, J. Menard, S. Gerhardt, J. Canick, A. McClean,
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,
18th International Spherical Torus Workshop, Princeton, November 2015 Magnetic Configurations  Three comparative configurations:  Standard Divertor (+QF)
Member of the Helmholtz Association Particle Confinement Control with Resonant Magnetic Perturbations (RMP) at TEXTOR-DED Oliver Schmitz 1, J.W. Coenen.
BOUT++ Towards an MHD Simulation of ELMs B. Dudson and H.R. Wilson Department of Physics, University of York M.Umansky and X.Xu Lawrence Livermore National.
Neoclassical Effects in the Theory of Magnetic Islands: Neoclassical Tearing Modes and more A. Smolyakov* University of Saskatchewan, Saskatoon, Canada,
Page 1 Alberto Loarte- NSTX Research Forum st - 3 rd December 2009  ELM control by RMP is foreseen in ITER to suppress or reduce size of ELM energy.
DIII-D RMP simulations: enhanced density transport and rotation screening V.A. Izzo, I. Joseph NIMROD meeting:
NSTX Meeting name – abbreviated presentation title, abbreviated author name (??/??/20??) Goals of NSTX Advanced Scenario and Control TSG Study, implement,
Pedestal Characterization and Stability of Small-ELM Regimes in NSTX* A. Sontag 1, J. Canik 1, R. Maingi 1, J. Manickam 2, P. Snyder 3, R. Bell 2, S. Gerhardt.
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.
G. Matsunaga 1), M. Okabayashi 2), N. Aiba 1), J. A. Boedo 3), J. R. Ferron 4), J. M. Hanson 5), G. Z. Hao 6), W. W. Heidbrink 7), C. T. Holcomb 8), Y.
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.
1 Edge Characterization Experiment in High Performance (highly shaped) Plasmas R. J. Maqueda (Nova Photonics) R. Maingi (ORNL) V. Soukhanovskii (LLNL)
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
Effects of external non-axisymmetric perturbations on plasma rotation L. Frassinetti, P.R. Brunsell, J.R. Drake, M.W.M. Khan, K.E.J. Olofsson Alfvén Laboratory,
Stellarator Divertor Design and Optimization with NCSX Examples
Features of Divertor Plasmas in W7-AS
Non-linear MHD simulations for ITER
Finite difference code for 3D edge modelling
E3D: status report and application to DIII-D
Andrew Kirk on behalf of
L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.
Influence of energetic ions on neoclassical tearing modes
Yasuhiro Suzuki for the LHD experiment group
Non-Local Effects on Pedestal Kinetic Ballooning Mode Stability
Stabilization of m/n=1/1 fishbone by ECRH
Max-Planck Institut für Plasmaphysik Garching
Presentation transcript:

DIII-D 3D edge physics capabilities: modeling, experiments and physics validation Presented by T.E. Evans 1 I. Joseph 2, R.A. Moyer 2, M.J. Schaffer 1, A. Runov 3, R. Schneider 3, S.V. Kasilov 4, M.E. Fenstermacher 5, M. Groth 5, J.W. Watkins 6 1 GA, 2 UCSD, 3 MPI-Griefswald, 4 Kharkov IPT, 5 LLNL, 6 SNL, Presented at NCSX Research Forum 2006 December 8 th, 2006

DIII-D has generated capability in 3D edge physics modeling & interest in validation of physical models DIII-D’s most successful ELM suppression techniques rely on the essential 3D physics of non-axisymmetric perturbations – RMP H-mode: externally induced resonant fields – QH-mode: internally generated, nonlinearly saturated EHO hypothesis 3D equilibrium reconstructions are critical to validating underlying physics mechanisms –DIII-D plasmas can be used to benchmark 3D equilibrium codes VMEC, V3FIT, PIES, EFIT + ideal DCON response, … –Field line tracing used to explore field structure: TRIP3D (GA) –Braginskii 2-fluid codes used for equilibrium transport E3D (MPI-Greifswald) thermal transport in stochastic fields EMC3-EIRENE (FZ-Jülich) currently used by TEXTOR collaborators –MHD: NIMROD, M3D, JOREK

Key physics issues for DIII-D are clearly important for NCSX Can we validate the physics of resonant magnetic field penetration? –MHD modeling by NIMROD, M3D, JOREK codes can be used to assess physics of forced reconnection at finite toroidal flow –Extended MHD models can test various neoclassical predictions for viscosity –Parallel kinetic closures can extend validity to lower collisionality ELM peeling-ballooning stability needs to be reassessed in 3D equilibria –Experimental results from DIII-D and JET seem to indicate that the Type-I ELM threshold can be continuously tuned by applying external perturbations –MHD modeling by NIMROD, M3D, JOREK – ELITE-3D??? will be required for efficient analysis of experimental stability threshold

Magnetic footprint structures predicted by TRIP3D/E3D have been observed on Xpt/IR-TV Xpt-TV ISP: filtered D  msTRIP3D ISP: field lines ms Asymmetric footprint observations can be used to validate the magnetic field model E3D ISP heat flux ms I-coil only

q 95 =3.55 Drift Effects? Detailed OSP footprint can be compared to strike point sweep of Langmuir probe array LPA: ms J sat at  =180 o Proper in-out asymmetry may require asymmetric D anom Drift effects? extra bump in private flux zone requires new explanation E3D: ms ISP at  =150 o and OSP at  =180 o

Paradox: the RMP primarily controls peeling-ballooning stability through particle transport! n decreases, not T

Resolution? pedestal toroidal rotation and E r change promptly when RMP is applied at q95 resonance H-mode pedestal v  spins up and E r well narrows.

Summary Experience gained at DIII-D in 3D edge physics may be valuable for NCSX –Validation of 3D edge models Equilibrium reconstruction Field line integration and mapping Fluid transport (heat, particle and momentum) Resonant field screening (flow and pressure) Divertor footprints MHD stability (peeling-ballooning, forced reconnection, etc.) –Availability of experimental data in high power discharges Developing 3D diagnostic capabilities Developing 3D boundary control systems and technology

N = 3 perturbations induce edge stochastic layer which destroys axisymmetric flux surfaces Color = # toroidal transits for escape (red=201 max, black<10) Caveat: no plasma response in this model

Detailed OSP footprint can be compared to strike point sweep of Langmuir probe array E3D heat flux simulation E3D heat flux qualitatively matches measured fluxes Quantitative agreement will require …? LPA J sat at  DIII-D =180 o ms q 95 =3.55 Due to drifts?

E3D simulations show that the tangle also efficiently guides heat flux to the divertor targets Private flux region still exists due to short divertor connection length The field lines cannot sample the lower branches of the tangle

As RMP , predicted tangle structure grows & heats at 4650 ms BC’s: T e = 1.6 keV, T i = 2.6 keV at  n = 77% Te (eV): I-coil (kA): 0 (2D) 1 2 3

As RMP  predicted edge temperature cools at 4650 ms BC’s: T e = 1.6 keV, T i = 2.6 keV at  n = 77% Constant temperature BC’s Edge stochastic layer cools relative to pedestal –remains hot compared to SOL TeTe TiTi

Escaping field lines are trapped by the invariant manifolds which exit the X-point Backward Escape Upper “Stable” manifold Forward escape Upper “Unstable” manifold The outline of the field line escape pattern traces out the surfaces of the invariant manifold The homoclinic tangle encodes the structure of chaos ms Color = field line length red<2km blue<200m

The tangle forms non-axisymmetric magnetic footprints which have been experimentally observed T e reflects a superposition of both upper invariant manifolds Multiple magnetic footprint stripes observed during I-coil operation : filtered D  Xpt-TV : filtered CIII Xpt-TV