Interplay between confinement, turbulence and magnetic topology Nils P. Basse MIT Plasma Science and Fusion Center This proposal originates from density.

Slides:



Advertisements
Similar presentations
Glenn Bateman Lehigh University Physics Department
Advertisements

Chalkidikhi Summer School Plasma turbulence in tokamaks: some basic facts… W.Fundamenski UKAEA/JET.
The Reversed Field Pinch: on the path to fusion energy S.C. Prager September, 2006 FPA Symposium.
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
1 G.T. Hoang, 20th IAEA Fusion Energy Conference Euratom Turbulent Particle Transport in Tore Supra G.T. Hoang, J.F. Artaud, C. Bourdelle, X. Garbet and.
Institut für Plasmaforschung Universität Stuttgart Long-distance correlation of fluctuations under strong ExB shear in TJ-K P. Manz, M. Ramisch, U. Stroth.
IAEA - FEC2004 // Vilamoura // // EX/4-5 // A. Staebler – 1 – A. Staebler, A.C.C Sips, M. Brambilla, R. Bilato, R. Dux, O. Gruber, J. Hobirk,
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS V. Vershkov, L.G. Eliseev, S.A. Grashin. A.V. Melnikov, D.A.
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.
Fast imaging of global eigenmodes in the H-1 heliac ABSTRACT We report a study of coherent plasma instabilities in the H-1 plasma using a synchronous gated.
Nils P. Basse Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge, MA USA ABB seminar November 7th, 2005 Measurements.
Parallel and Poloidal Sheared Flows close to Instability Threshold in the TJ-II Stellarator M. A. Pedrosa, C. Hidalgo, B. Gonçalves*, E. Ascasibar, T.
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
Valisa et al C-mod Ideas Forum, 8 April Electron heating and Ni / Mo Pump Out L Carraro, I Predebon, ME Puiatti, M Valisa ( Consorzio RFX Padova)
Profile Measurement of HSX Plasma Using Thomson Scattering K. Zhai, F.S.B. Anderson, J. Canik, K. Likin, K. J. Willis, D.T. Anderson, HSX Plasma Laboratory,
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
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.
Interplay between confinement, turbulence and magnetic topology Nils P. Basse, S. Zoletnik 1, W. L. Rowan 2 et al. MIT Plasma Science and Fusion Center.
Interplay between magnetic topology, density fluctuations and confinement in high-  Wendelstein 7-AS plasmas Nils P. Basse 1 Association EURATOM – Risø.
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
Characterization of core and edge turbulence in L- and H-mode Alcator C-Mod plasmas Outline: Alcator C-Mod tokamak Fluctuation diagnostics Low to high.
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
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.
CHI Run Summary for March 10-12, 31 & April 9, 2008 Flux savings from inductive drive of a Transient CHI started plasma (XP817) R. Raman, B.A. Nelson,
TJ-II Results from Helical Axis Stellarators - ICPP 2000 TJ-II Heliac, CIEMAT, Spain R = 1.5 m, a < 0.22 m, 4 periods B 0 < 1.2 T P ECRH < 600 kW from.
HT-7 ASIPP The Influence of Neutral Particles on Edge Turbulence and Confinement in the HT-7 Tokamak Mei Song, B. N. Wan, G. S. Xu, B. L. Ling, C. F. Li.
Physics of fusion power Lecture 12: Diagnostics / heating.
Measurements of plasma turbulence by laser scattering in the Wendelstein 7-AS stellarator Nils P. Basse 1,2, S. Zoletnik, M. Saffman, P. K. Michelsen and.
Active Control of MHDinstabilitiy 2002/11/19 S.Ohdachi et.al. Sawtooth-like phenomena in LHD S. Ohdachi, S.Yamamoto, K. Toi, K. Y.Watanabe, S.Sakakibara,
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority ITB formation and evolution with co- and counter NBI A. R. Field, R. J. Akers,
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
FEC 2006 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower.
Parallel Correlation of SOL Turbulence S.J. Zweben, F. Scotti, J.W. Ahn, T. Gray, M. Jaworski, S. Kubota, R. Maqueda, N. Mandell, D. Smith, V. Soukhanovskii.
T. Bolzonella – 9 February 2011 – RFX-mod programme workshop TF1: Physics integration for high performance RFP Proposals and discussion T. Bolzonella,
Multi-scale turbulence experiment in HT-7 takamak Li Yadong Li Jiangang Zhang Xiaodong Ren Zhong Zhang Tou Lin Shiyao and HT-7 Team Institute of plasma.
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Taming The Physics For Commercial Fusion Power Plants ARIES Team Meeting.
Solenoid Free Plasma Start-up Mid-Run Summary (FY 2008) R. Raman and D. Mueller Univ. of Wash. / PPPL 16 April 2008, PPPL 1 Supported by Office of Science.
MCZ MCZ NCSX Mission Acquire the physics data needed to assess the attractiveness of compact stellarators; advance understanding.
Distributions of plasma parameters and observation of intermittency in edge plasma of SUNIST W H Wang, Y X He, and SUNIST Team Department of Engineering.
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
Simulations of turbulent plasma heating by powerful electron beams Timofeev I.V., Terekhov A.V.
Scaling experiments of perturbative impurity transport in NSTX D. Stutman, M. Finkenthal Johns Hopkins University J. Menard, E. Synakowski, B. Leblanc,R.
52nd Annual Meeting of the Division of Plasma Physics, November , 2010, Chicago, Illinois 5-pin Langmuir probe configured to measure floating potential.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
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.
Tuomas Tala 1/16 ITPA TC Meeting, Princeton, USA 5 October – 7 October 2009 T. Tala (JET, DIII-D), W. Solomon (DIII-D, JET, NSTX) and S. Kaye, L.F. Delgado-
HT-7 Proposal of the investigation on the m=1 mode oscillations in LHCD Plasmas on HT-7 Exp2005 ASIPP Youwen Sun, Baonian Wan and the MHD Team Institute.
Lower Hybrid Wave Coupling and Current Drive Experiments in HT-7 Tokamak Weici Shen Jiafang Shan Handong Xu Min Jiang HT-7 Team Institute of Plasma Physics,
Hard X-rays from Superthermal Electrons in the HSX Stellarator Preliminary Examination for Ali E. Abdou Student at the Department of Engineering Physics.
57th Annual Meeting of the Division of Plasma Physics, November , Savannah, Georgia Equilibrium Reconstruction Theory and Modeling Optimized.
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
Decrease of transport coefficients in the plasma core after off-axis ECRH switch-off K.A.Razumova and T-10 team.
G.Y. Park 1, S.S. Kim 1, T. Rhee 1, H.G. Jhang 1, P.H. Diamond 1,2, I. Cziegler 2, G. Tynan 2, and X.Q. Xu 3 1 National Fusion Research Institute, Korea.
9-12 Sept. 2002E. BARBAT0-ENEA, TTF, Cordoba1 Electron Internal Transport barriers by LHCD and ECRH in FTU-high density plasmas E. Barbato Associazione.
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik1, D.L. Brower2, C. Deng2,
High-beta Program 3 June 2002 Objective: Investigate effect of toroidal currents on high-b performance: 1. Low-iota: discharges with current ramp and constant.
Turbulence associated with the control of internal transport barriers
in tokamaks and stellarators
Center for Plasma Edge Simulation
First Experiments Testing the Working Hypothesis 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,
Current-Hole Experiments have been performed on JET and JT-60
XGC simulation of CMOD edge plasmas
20th IAEA Fusion Energy Conference,
The GDT device at the Budker Institute of Nuclear Physics is an experimental facility for studies on the main issues of development of fusion systems based.
Reflectometry measurements of turbulence in Alcator C-Mod plasmas
Density Fluctuations as an Intrinsic Mechanism to Keep Self-consistent Shape of Pressure Profile EX/11-2Rb Density fluctuations significantly rises in.
Presentation transcript:

Interplay between confinement, turbulence and magnetic topology Nils P. Basse MIT Plasma Science and Fusion Center This proposal originates from density fluctuation studies of W7-AS plasmas with the LOTUS small-angle scattering diagnostic. Observations on the connection between stored energy and the edge rotational transform: Low shear (no net plasma current): The stored energy is very sensitive to small changes of the edge rotational transform, optimum values close to low-order rational values. High shear (net plasma current): The stored energy is large regardless of the edge rotational transform.

Interplay between confinement, turbulence and magnetic topology Model has been developed, where the electron heat conductivity is described by three contributions: 1.Neoclassical transport. 2.Turbulent transport. 3.Transport close to low-order rational surfaces. To verify changes in turbulent transport when the edge rotational transform is modified in low-shear plasmas, discharges were developed where slow, reproducible confinement transitions were created by driving a small plasma current. Large correlated changes were observed in density, magnetic and H- alpha fluctuations.

Interplay between confinement, turbulence and magnetic topology Can we construct similar slow confinement transitions in C-Mod? W7-AS current ramp target parameters: Medium density, kept constant by feedback gas puffing to minimize particle transport effects. Low ECRH power. Low shear. Transition is basically a collapse of the electron temperature. C-Mod: Try Ohmic and low power ICRH. Low shear would certainly be an issue in C-Mod, are there ways to reduce the shear appreciably (fast ramping, early heating)? Current penetration time in C-Mod? If suitable target can be developed, document stored energy versus q95. Thereafter, perform current ramp experiments. Later phase: Use LHCD to modify q-profile, create low shear areas.