OVERVIEW of FTU RESULTS
|
|
- Dana Casey
- 5 years ago
- Views:
Transcription
1 OVERVIEW of FTU RESULTS Angelo A. Tuccillo on behalf of FTU and ECRH teams and A. Alekseyev, V. Lazarev, S. Mirnov (TRINITI, Troitsk, RF) A. Biancalani, F. Pegoraro (University of Pisa) L. Chen (University of California-Irvine/Zhejiang University) U. de Angelis (University of Naples) I.E. Lyublinski, A. Vertkov (FSUE Red Star, Moscow, RF) J.R. Martin olis (Universidad Carlos III, Madrid, SP) S. Ratynskaia, S. Annibaldi (Royal Institute of Technology, SE) R. Zagórski (IPPL, Warsaw, PL)
2 - New Diagnostics OUTLINE (Overview FTU results) - Improved Plasmas with LLL G. Mazzitelli et al. EX-P4-6 - Electron Fishbones studies R. Cesario et al. EX-P Shear-Alfvén Waves in presence of a magnetic island A. Biancalani et al. TH/P3-5 - Disruption Avoidance by ECRH B. Esposito et al. EX/7-3Ra - Dust dynamic studies C. Castaldo et al. EX/P4-5 - Future plans Compact (circular) all metallic device R=0.93m, a=0.3m, Bt 8T, Ip 1.6MA LHCD P 2 MW f=8 GHz ECRH P 1.5MW f=140 GHz Changeable materials Poloidal Limiter Capillar Porous System Liquid Lithium Limiter Molibdenum Toroidal Limiter
3 New Hardware Since last IAEA-FEC, two new diagnostics have been installed on FTU: - A prototype time-of-flight refractometer at 60 GHz, has been successfully tested measurements are fully in agreement with CO 2 interferometer data at ITER density and magnetic field. This system has reduced size, do not require mirrors inside the vessel and is not affected by fringe jumps good candidate for the ITER density feedback control. The final system to be installed on FTU with two frequencies is under development in collaboration with TRINITI institute (Moscow). - Oblique ECE: Is already producing preliminary data
4 New Hardware: Oblique ECE 4<#< ECE emission at 72, f= GHz is in agreement with emission at 90, f=280 GHz during Ohmic phase and moderate heating during ECRH. The 72 emission becomes lower than perpendicular, with broader second harmonic spectrum, during high heating ECRH phase ECH
5 New Hardware: Oblique ECE 5<#< ECE emission at 77 is higher than the perpendicular emission during LH, but lower than expected. Code interpretation is in progress N e =9x10 13 m -3 P LH =1.2 MW L H
6 Improved performance with Liquid Lithium Limiter - I LLL is now a routine tool in FTU operations. The high density regime with peaked profiles, that was just obtained at the time of last IAEA-FEC has been extensively studied n e In the peaked, high density phase electron thermal conductivity χ e decreases to values typical of FTU Saturated Ohmic Confinement In the high-peaked phase transport keeps being dominated by electrons. Ion thermal conductivity χ i remains close to its neoclassical value even at highest densities (1.6*n Greenwald )
7 Improved performance with Liquid Lithium Limiter - II The enhanced confinement seems to be triggered when the density peaking factor overcomes the threshold value of Regardless of the density value, almost all the 0.5 MA discharges with LLL tend to peak the density profile above the threshold value. Analysis in progress to identify the mode/turbulence stabilisation mechanism responsible of the improvement
8 Improved performance with Liquid Lithium Limiter-III The general behaviour of confinement time dependence on density in FTU has been documented in the past and shows the typical transition from the linear (LOC) regime to the saturated (SOC) regime n e
9 Improved performance with Liquid Lithium Limiter-III The general behaviour of confinement time dependence on density in FTU has been documented in the past and shows the typical transition from the linear (LOC) regime to the saturated (SOC) regime. High density discharges with LLL at 0.5MA show same behaviour but with higher threshold, ~70ms with respect to ~50 of the historical FTU data base n e
10 Improved performance with Liquid Lithium Limiter-III Similarities with the enhanced SOC threshold observed in multiple-pellet PEP discharges, which showed in their turn a very high peaked density profiles, reinforces the hypothesis that the enhanced confinement regime obtained with LLL could be also related to a higher density gradient in the plasma bulk, but higher current data Ip > 0.8 MA are needed
11 Electron Fishbones Studies-I At last FEC, FTU reported evidence of e-fishbones during high power LHCD A non linear dynamic model was used for interpreting the experimental evidence A systematic exploration of FTU plasma parameters and LH power has initiated to validate theory (F. Zonca et al, Nuc. Fusion ) MHD spectrograms in three similar sawtoothing shots with: No LH 0.3 MWLH power 0.5 MW LH power V. Pericoli et al, OV/3-4, FEC-06 F. Zonca et al, TH/3-2 Fishbone signature with LH only
12 Electron Fishbones Studies-II Soft-X ray Hard-x: 40-60keV Soft x-ray tomography detects the mode and provides time basis for Hard x-ray integration On mode time scale (0.1ms) e - flip-flops around mode localisation (kink structure) Fast FEB camera records perpendicular Hard x-ray emission giving indication on LH generated fast electrons 0.76 Time (s) ms integration sliding window analysis indicates MHD enhanced e - transport
13 Shear Alfvén Waves in presence of magnetic island-i - SAWs in a nonuniform equilibrium experience continuum damping near the resonant surfaces. - Understanding the continuous spectrum structure is relevant for plasma stability. - SAW continuous spectrum is modified by the interaction with magnetic islands BAE-CAP is shifted in space to the separatrix position BAE-CAP frequency is not modified by the island. New continuum accumulation points and new gaps in the continuous spectrum at the O- point. - New magnetic island induced Alfvén Eigenmodes (MiAE), excited via wave-particle resonances, provided that the island size is wide with respect to the mode
14 SAW in presence of magnetic island-ii - Shear Alfvén modes correlated with magnetic islands in FTU OH plasmas - Modes are seen in pairs --> Doppler shift of modes born in the island reference frame - The pair averaged frequency grows with island size consistently with theoretical continuum deformation - MiAE are localized in the center of the island and could be observed by ECE or soft X-ray, not by Mirnov coils - MiAE frequency expected higher than the BAE-CAP, while observed mode frequencies are lower than the BAE-CAP. The observed modes are BAE nonlinearly interacting with the magnetic island, via 3-wave coupling - MiAE-CAP frequency depends on mode numbers and magnetic island size. These frequency scalings could be used as novel magnetic island diagnostic.
15 Disruption Avoidance with ECRH-I After ECRH Before ECRH Disruption avoidance: when ECRH (no CD) is deposited (ECWGB 3D code, S. Nowak et al., PoP ) at resonant surface (q=3/2, q=2, q=3 in LBO induced disruptions) by poloidally steering 1-3 beams in constant magnetic field plasmas However current quench delayed when deposition radius is close to the MHD resonant surface
16 Disruption Avoidance with ECRH-II Modes couple before disruption, likely to be toroidal sidebands of each other and their harmonics Control of one mode leads to the simultaneous control of the others (B. Esposito et al., Phys. Rev. Lett. 100, (2008) Aiming at 2/1 mode (2.5 cm FWHW deposition profile, P ECRH =1.0 MW, P abs = 0.6 MW, r dep = 14 cm) leads simultaneously to the decrease of the 3/1 mode, 5 cm apart with ~2 cm island width ECRH cannot affect directly the 3/1 mode I p T e0 ECRH MHD Island width and radius measured from soft-x tomographic reconstruction
17 Disruption Avoidance with ECRH-III 17<#< modified Rutherford equation (including asymmetric island parameters) and island rotation frequency equation used to study island evolution modes involved in the disruption found to be conventional tearing modes stabilized by a strong local ECRH heating ECRH reduces the growth of the width of the island which is subsequently slowed down by viscous and inertial torques
18 18<#< Dust dynamics studies-i: Dust-impact ionization The fluctuations in the ion saturation current detected by two adjacent (6 mm distance in poloidal direction) electrostatic probes are uncorrelated only for large (> 6 rms) events. Interpretation in terms of dust-impact ionization is supported by impact craters observed on the probe surface
19 Dust dynamics studies-ii: laser light scattering - Characterization of dust present in FTU after disruptions by laser scattering at laser λ = 1064 nm - Rayleigh modelling for particle radius 0.1 μm > a > 30 nm The average dust density is about 10 7 m -3 The size distribution follows a power law σ For larger particles the generalized Mie scattering theory should be used, taking into account spheroidal shape parameters and off-axis Gaussian-beam illumination: Rayleigh scattering approximation underestimates the particle radii by a factor Nonlinear laser-dust interaction is suggested by the occurrence of a broadband emission, well correlated in time with the light scattered at the laser wavelength 19<#<
20 New Hardware: under realisation Refurbishment of LH and ECRH for full power operations by end of 2009 New ECRH Launcher able of real time steering for: - mode control - large toroidal angles for CD and - electron Bernstein conversion for heating high density plasmas obtained with Lithized wall Collective Thomson Scattering in the ITER (frequency/magnetic field) configuration
21 NEW ECRH LAUNCHER FOR REAL TIME EXPERIMENT FTU new ECRH launcher Type: front steering Number of lines 2 Mirrors for each line 5 Movable optics for zooming 2 each line Waist into plasma (from-to) mm Minor radius covered 0-25 cm corresponding to: >75% plasma Poloidal angle (upper line) -35 to +25 Toroidal angle (continuous) -35 to +35 Reference angular velocity 0.1 /ms The upgrade of the ECRH antenna includes 2 steerable, real time controlled mirrors with fast movement in poloidal and toroidal directions. Techniques for plasma or instability control can be fully developed and tested. New capabilities of beam shaping (zooming) are for the first time implemented. CTS proof of principle in ITER like configuration.
22 OVERVIEW of FTU RESULTS Angelo A. Tuccillo on behalf of FTU and ECRH teams and A. Alekseyev, V. Lazarev, S. Mirnov (TRINITI, Troitsk, RF) A. Biancalani, F. Pegoraro (University of Pisa) L. Chen (University of California-Irvine/Zhejiang University) U. de Angelis (University of Naples) I.E. Lyublinski, A. Vertkov (FSUE Red Star, Moscow, RF) J.R. Martin olis (Universidad Carlos III, Madrid, SP) S. Ratynskaia, S. Annibaldi (Royal Institute of Technology, SE) R. Zagórski (IPPL, Warsaw, PL)
23 - New Diagnostics OUTLINE (Overview FTU results) - Improved Plasmas with LLL G. Mazzitelli et al. EX-P4-6 - Electron Fishbones studies R. Cesario et al. EX-P Shear-Alfvén Waves in presence of a magnetic island A. Biancalani et al. TH/P3-5 - Disruption Avoidance by ECRH B. Esposito et al. EX/7-3Ra - Dust dynamic studies C. Castaldo et al. EX/P4-5 - Future plans Compact (circular) all metallic device R=0.93m, a=0.3m, Bt 8T, Ip 1.6MA LHCD P 2 MW f=8 GHz ECRH P 1.5MW f=140 GHz Changeable materials Poloidal Limiter Capillar Porous System Liquid Lithium Limiter Molibdenum Toroidal Limiter
Overview of the FTU Results
1 Overview of the FTU Results A.A. Tuccillo 1), A. Alekseyev 2), B. Angelini 1) S.V. Annibaldi 3), M.L. Apicella 1), G. Apruzzese 1), J. Berrino 4), E. Barbato 1), A. Bertocchi 1), A. Biancalani 5), W.
More informationOverview of the FTU results OV/3-4
Overview of the FTU results OV/3-4 V. Pericoli Ridolfini, on behalf of FTU team and 1 ECH team A. Alekseyev 2, B. Angelini, S.V. Annibaldi, M.L. Apicella, G. Apruzzese, E. Barbato, J. Berrino 1, A. Bertocchi,
More informationShear Alfvén Wave Continuous Spectrum in the Presence of a Magnetic Island
1 TH/P3-5 Shear Alfvén Wave Continuous Spectrum in the Presence of a Magnetic Island A. Biancalani 1), L. Chen 2) 3), F. Pegoraro 1), F. Zonca 4), S. V. Annibaldi 5), A. Botrugno 4), P. Buratti 4) and
More informationOVERVIEW 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 informationRecent 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 informationMHD instability driven by supra-thermal electrons in TJ-II stellarator
MHD instability driven by supra-thermal electrons in TJ-II stellarator K. Nagaoka 1, S. Yamamoto 2, S. Ohshima 2, E. Ascasíbar 3, R. Jiménez-Gómez 3, C. Hidalgo 3, M.A. Pedrosa 3, M. Ochando 3, A.V. Melnikov
More informationObservation of Neo-Classical Ion Pinch in the Electric Tokamak*
1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,
More informationInfluence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator
EX/P- Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator Á. Cappa, F. Castejón, T. Estrada, J.M. Fontdecaba, M. Liniers and E. Ascasíbar Laboratorio Nacional de Fusión CIEMAT,
More informationDIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH
DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK
More informationCharacterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod
1 EX/P4-22 Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.
More informationECRH Results during Current Ramp-up and Post-Pellet Injection in FTU Plasma
18 th IAEA Fusion Energy Conference, Sorrento, Italy, October 4-10, 2000 ECRH Results during Current Ramp-up and Post-Pellet Injection in FTU Plasma Paper EX6/3 presented by G. Bracco FTU Group, ECRH Group*
More informationCombined LH and ECH Experiments in the FTU Tokamak
Combined LH and ECH Experiments in the FTU Tokamak V. Pericoli Ridolfini, Y. Peysson 1, R. Dumont 1, G. Giruzzi 1, G. Granucci 2, L. Panaccione, L. Delpech 1, B. Tilia, FTU team, ECH team 2 Associazione
More informationElectron temperature barriers in the RFX-mod experiment
Electron temperature barriers in the RFX-mod experiment A. Scaggion Consorzio RFX, Padova, Italy Tuesday 5 th October 2010 ADVANCED PHYSICS LESSONS 27/09/2010 07/10/2010 IPP GARCHING JOINT EUROPEAN RESEARCH
More informationPlasma Start-Up Results with EC Assisted Breakdown on FTU
1 EXW/P2-03 Plasma Start-Up Results with EC Assisted Breakdown on FTU G. Granucci 1), G. Ramponi 1), G. Calabrò 2), F. Crisanti 2), G. Ramogida 2), W. Bin 1), A. Botrugno 2), P.Buratti 2), O. D Arcangelo1,
More informationReduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX
1 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1), D.L. Brower 2), C. Deng 2), D.T. Anderson 1), F.S.B. Anderson 1), A.F.
More informationObservations 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 informationAdvanced 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 informationPhysics and Operations Plan for LDX
Physics and Operations Plan for LDX Columbia University A. Hansen D.T. Garnier, M.E. Mauel, T. Sunn Pedersen, E. Ortiz Columbia University J. Kesner, C.M. Jones, I. Karim, P. Michael, J. Minervini, A.
More informationPerformance limits. Ben Dudson. 24 th February Department of Physics, University of York, Heslington, York YO10 5DD, UK
Performance limits Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 24 th February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 24) Previously... In the last few
More informationHeating 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 informationRecent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science
Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant
More informationOverview 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 informationEffect of ideal kink instabilities on particle redistribution
Effect of ideal kink instabilities on particle redistribution H. E. Ferrari1,2,R. Farengo1, P. L. Garcia-Martinez2, M.-C. Firpo3, A. F. Lifschitz4 1 Comisión Nacional de Energía Atómica, Centro Atomico
More informationRecent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE
Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE M. Uchida, Y. Nozawa, H. Tanaka, T. Maekawa Graduate School of Energy Science, Kyoto University
More informationImpact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak
Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak M. Garcia-Munoz M. A. Van Zeeland, S. Sharapov, Ph. Lauber, J. Ayllon, I. Classen, G. Conway, J. Ferreira,
More informationC-Mod Transport Program
C-Mod Transport Program PAC 2006 Presented by Martin Greenwald MIT Plasma Science & Fusion Center 1/26/2006 Introduction Programmatic Focus Transport is a broad topic so where do we focus? Where C-Mod
More information(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time
Studies of Spherical Tori, Stellarators and Anisotropic Pressure with M3D 1 L.E. Sugiyama 1), W. Park 2), H.R. Strauss 3), S.R. Hudson 2), D. Stutman 4), X-Z. Tang 2) 1) Massachusetts Institute of Technology,
More informationNoninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE
1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.
More informationECRH Results during Current Ramp-up and Post-Pellet Injection in FTU Plasma
ECRH Results during Current Ramp-up and Post-Pellet Injection in FTU Plasma G. Bracco 1), A. Bruschi 1), P. Buratti 1), S. Cirant 2), F. Crisanti 1), B. Esposito 1), D. Frigione 1), E. Giovannozzi 1),
More informationLower 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 informationOn the physics of shear flows in 3D geometry
On the physics of shear flows in 3D geometry C. Hidalgo and M.A. Pedrosa Laboratorio Nacional de Fusión, EURATOM-CIEMAT, Madrid, Spain Recent experiments have shown the importance of multi-scale (long-range)
More informationICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks
ICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks Y. Lin, J.E. Rice, S.J. Wukitch, M.J. Greenwald, A.E. Hubbard, A. Ince- Cushman, L. Lin, E.S. Marmar, M. Porkolab, M.L.
More informationFirst plasma operation of Wendelstein 7-X
First plasma operation of Wendelstein 7-X R. C. Wolf on behalf of the W7-X Team *) robert.wolf@ipp.mpg.de *) see author list Bosch et al. Nucl. Fusion 53 (2013) 126001 The optimized stellarator Wendelstein
More informationPhase ramping and modulation of reflectometer signals
4th Intl. Reflectometry Workshop - IRW4, Cadarache, March 22nd - 24th 1999 1 Phase ramping and modulation of reflectometer signals G.D.Conway, D.V.Bartlett, P.E.Stott JET Joint Undertaking, Abingdon, Oxon,
More informationImproved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus)
Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus) PD/P-01 C. Castaldo 1), R. Cesario 1), Y, Andrew 2), A. Cardinali 1), V. Kiptly 2), M. Mantsinen
More informationProgress of Confinement Physics Study in Compact Helical System
1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress
More informationSTABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK
GA A24738 STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK by T.C. LUCE, C.C. PETTY, D.A. HUMPHREYS, R.J. LA HAYE, and R. PRATER JULY 24 DISCLAIMER This
More informationITB Transport Studies in Alcator C-Mod. Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co
Transport Studies in Alcator C-Mod Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co With Contributions from: I. Bespamyatnov, P. T. Bonoli*, D. Ernst*, M.
More informationThe FTU facilities. Regarding the the control and data acquisition system, last year we carried out the following activities:
The FTU facilities FTU Machine Summary of the machine operation During 2005, the machine operated at the high level of 91% of successful pulses. The experimental activity started in March and went on till
More informationStudies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D
Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of
More informationPlan 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 informationBehavior of Compact Toroid Injected into the External Magnetic Field
Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa
More informationSimulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD
1 Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD Y. Todo 1), N. Nakajima 1), M. Osakabe 1), S. Yamamoto 2), D. A. Spong 3) 1) National Institute for Fusion Science,
More informationThe role of stochastization in fast MHD phenomena on ASDEX Upgrade
1 EX/P9-10 The role of stochastization in fast MHD phenomena on ASDEX Upgrade V. Igochine 1), O.Dumbrajs 2,3), H. Zohm 1), G. Papp 4), G. Por 4), G. Pokol 4), ASDEX Upgrade team 1) 1) MPI für Plasmaphysik,
More informationC-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center
C-Mod Core Transport Program Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly
More informationOverview 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 informationFormation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )
Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University
More informationLocalized Electron Cyclotron Current Drive in DIII D: Experiment and Theory
Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. Lin-Liu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,
More informationFirst Experiments Testing the Working Hypothesis in HSX:
First Experiments Testing the Working Hypothesis in HSX: Does minimizing neoclassical transport also reduce anomalous transport? J. N. Talmadge HSX Plasma Laboratory University of Wisconsin-Madison Special
More informationConfinement Studies during LHCD and LHW Ion Heating on HL-1M
Confinement Studies during LHCD and LHW Ion Heating on HL-1M Y. Liu, X.D.Li, E.Y. Wang, J. Rao, Y. Yuan, H. Xia, W.M. Xuan, S.W. Xue, X.T. Ding, G.C Guo, S.K. Yang, J.L. Luo, G.Y Liu, J.E. Zeng, L.F. Xie,
More informationNIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997
NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU General Atomics Nimrod Project Review Meeting July 21 22, 1997 Work supported by the U.S. Department of Energy under Grant DE-FG03-95ER54309 and Contract
More informationMacroscopic Stability Research on Alcator C-Mod: 5-year plan
Macroscopic Stability Research on Alcator C-Mod: 5-year plan Presented by R. Granetz Alcator C-Mod PAC 06-08 Feb 2008 Principal MHD Research Topics in the Next 5-year Plan Effects of non-axisymmetric fields
More informationResistive Wall Mode Control in DIII-D
Resistive Wall Mode Control in DIII-D by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil
More informationCurrent-driven instabilities
Current-driven instabilities Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 21 st February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously In the last
More informationOn tokamak plasma rotation without the neutral beam torque
On tokamak plasma rotation without the neutral beam torque Antti Salmi (VTT) With contributions from T. Tala (VTT), C. Fenzi (CEA) and O. Asunta (Aalto) 2 Motivation: Toroidal rotation Plasma rotation
More informationOPERATION OF ITER OVER A RANGE OF TOROIDAL FIELDS POSES CHALLENGES FOR THE ECH SYSTEM. What can the ECH system do at different toroidal fields?
OPERATION OF ITER OVER A RANGE OF TOROIDAL FIELDS POSES CHALLENGES FOR THE ECH SYSTEM Operation from the design field of 5.3 T to as low as 3.0 T claimed by ITER team What can the ECH system do at different
More informationResistive Wall Mode Observation and Control in ITER-Relevant Plasmas
Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas J. P. Levesque April 12, 2011 1 Outline Basic Resistive Wall Mode (RWM) model RWM stability, neglecting kinetic effects Sufficient for
More informationHybrid Kinetic-MHD simulations with NIMROD
simulations with NIMROD 1 Yasushi Todo 2, Dylan P. Brennan 3, Kwang-Il You 4, Jae-Chun Seol 4 and the NIMROD Team 1 University of Washington, Seattle 2 NIFS, Toki-Japan 3 University of Tulsa 4 NFRI, Daejeon-Korea
More informationActive MHD Control Needs in Helical Configurations
Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2, A. Reiman 1, and the W7-AS Team and NBI-Group. 1 Princeton Plasma
More informationStudy 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 informationReduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower 2, C. Deng 2, D.T.Anderson 1, F.S.B. Anderson 1, A.F. Almagri
More informationHIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES
HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,
More informationDiagnostics for Burning Plasma Physics Studies: A Status Report.
Diagnostics for Burning Plasma Physics Studies: A Status Report. Kenneth M. Young Princeton Plasma Physics Laboratory UFA Workshop on Burning Plasma Science December 11-13 Austin, TX Aspects of Plasma
More informationElectron Thermal Transport Within Magnetic Islands in the RFP
Electron Thermal Transport Within Magnetic Islands in the RFP Hillary Stephens University of Wisconsin Madison APS-DPP Meeting November 3, 2009 J.R. Amubel, M.T. Borchardt, D.J. Den Hartog, C.C. Hegna,
More informationExtension of High-Beta Plasma Operation to Low Collisional Regime
EX/4-4 Extension of High-Beta Plasma Operation to Low Collisional Regime Satoru Sakakibara On behalf of LHD Experiment Group National Institute for Fusion Science SOKENDAI (The Graduate University for
More informationExperimental Study of the Stability of Alfvén Eigenmodes on JET
IAEA FEC, Paper EX/P-7 Experimental Study of the Stability of Alfvén Eigenmodes on JET D.Testa,, A.Fasoli,, G.Fu 4, A.Jaun 3, D.Borba, P.de Vries 6, and JET-EFDA contributors [] Plasma Science and Fusion
More information2007 Nuclear Fusion and Fission, and Related Technologies Department
PROGRESS REPORT 2007 Nuclear Fusion and Fission, and Related Technologies Department ITALIAN NATIONAL AGENCY FOR NEW TECHNOLOGIES ENERGY AND THE ENVIRONMENT This report was prepared by the Scientific Publications
More informationELMs and Constraints on the H-Mode Pedestal:
ELMs and Constraints on the H-Mode Pedestal: A Model Based on Peeling-Ballooning Modes P.B. Snyder, 1 H.R. Wilson, 2 J.R. Ferron, 1 L.L. Lao, 1 A.W. Leonard, 1 D. Mossessian, 3 M. Murakami, 4 T.H. Osborne,
More informationActive and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod
Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod JUST DID IT. J A Snipes, N Basse, C Boswell, E Edlund, A Fasoli #, N N Gorelenkov, R S Granetz, L Lin, Y Lin, R Parker, M Porkolab, J
More informationOverview of the FTU results
Overview of the FTU results V. Pericoli-Ridolfini, A. Alekseyev 1, B. Angelini, S.V. Annibaldi, M.L. Apicella, G. Apruzzese, E. Barbato, J. Berrino 2, A. Bertocchi, W. Bin 2, F. Bombarda, G. Bracco, A.
More informationActive Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak
Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak M. Garcia-Munoz, S. E. Sharapov, J. Ayllon, B. Bobkov, L. Chen, R. Coelho, M. Dunne, J. Ferreira, A. Figueiredo, M. Fitzgerald, J. Galdon-Quiroga,
More informationObservation of modes at frequencies above the Alfvén frequency in JET
Observation of modes at frequencies above the Alfvén frequency in JET F. Nabais 1, D. Borba 1, R. Coelho 1, L. Fazendeiro 1, J. Ferreira 1, A. Figueiredo 1, L. Fitzgerald 2, P. Rodrigues 1, S. Sharapov
More informationHeating and Confinement Study of Globus-M Low Aspect Ratio Plasma
EX/P5- Heating and Confinement Study of Globus-M Low Aspect Ratio Plasma N.V. Sakharov ), V.V. Dyachenko ), B.B. Ayushin ), A.V. Bogomolov ), F.V. Chernyshev ), V.K. Gusev ), S.A. Khitrov ), N.A. Khromov
More informationTransport Improvement Near Low Order Rational q Surfaces in DIII D
Transport Improvement Near Low Order Rational q Surfaces in DIII D M.E. Austin 1 With K.H. Burrell 2, R.E. Waltz 2, K.W. Gentle 1, E.J. Doyle 8, P. Gohil 2, C.M. Greenfield 2, R.J. Groebner 2, W.W. Heidbrink
More informationPerformance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges
Performance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges R. C. Wolf, J. Hobirk, G. Conway, O. Gruber, A. Gude, S. Günter, K. Kirov, B. Kurzan, M. Maraschek, P. J.
More informationStudy of chirping Toroidicity-induced Alfvén Eigenmodes in the National Spherical Torus Experiment
Study of chirping Toroidicity-induced Alfvén Eigenmodes in the National Spherical Torus Experiment M. Podestà 1, R. E. Bell 1, A. Bortolon 2, N. A. Crocker 3, D. S. Darrow 1, E. D. Fredrickson 1, G.-Y.
More informationDetection of Dust Particles in FTU
1 Detection of Dust Particles in FTU C. Castaldo 1), E. Giovannozzi 1), S. Ratynskaia 2), G. Capobianco 3), M. De Angeli 4), U. de Angelis 5), M. Kretschmer 6), G. Maddaluno 1), C. Marmolino 2), G.E. Morfill
More informationProgressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.
Progressing Performance Tokamak Core Physics Marco Wischmeier Max-Planck-Institut für Plasmaphysik 85748 Garching marco.wischmeier at ipp.mpg.de Joint ICTP-IAEA College on Advanced Plasma Physics, Triest,
More informationTRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER
TRANSPORT PROGRAM C-Mod C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER C-MOD - OPPORTUNITIES AND CHALLENGES Prediction and control are the ultimate goals
More informationSpontaneous tokamak rotation: observations turbulent momentum transport has to explain
Spontaneous tokamak rotation: observations turbulent momentum transport has to explain Ian H Hutchinson Plasma Science and Fusion Center and Nuclear Science and Engineering Massachusetts Institute of Technology
More informationInitial Experimental Program Plan for HSX
Initial Experimental Program Plan for HSX D.T. Anderson, A F. Almagri, F.S.B. Anderson, J. Chen, S. Gerhardt, V. Sakaguchi, J. Shafii and J.N. Talmadge, UW-Madison HSX Plasma Laboratory Team The Helically
More informationThe measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak
The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak H. Furui, Y. Nagashima 2, A. Ejiri, Y. Takase, N. Tsujii, C. Z. Cheng,
More informationElectron Bernstein Wave (EBW) Physics In NSTX and PEGASUS
Electron Bernstein Wave (EBW) Physics In NSTX and PEGASUS G. Taylor 1, J.B. Caughman 2, M.D. Carter 2, S. Diem 1, P.C. Efthimion 1, R.W. Harvey 3, J. Preinhaelter 4, J.B. Wilgen 2, T.S. Bigelow 2, R.A.
More informationThe Li-wall Stellarator Experiment in TJ-II
The Li-wall Stellarator Experiment in TJ-II Laboratorio Nacional de Fusión. CIEMAT. Madrid. Spain Outlook Introduction Why Lithium? Li coating technique in TJ-II 2008 Results Particle recycling and confinement
More informationRole 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 informationMagnetic Diagnostics Basics
Abstract We report measurement of the equilibrium plasma current profiles in the Levitated Dipole Experiment (LDX) that exhibit a peak beta in excess of 10 percent. The beta of an LDX plasma is calculated
More informationElectron Bernstein Wave Heating in the TCV Tokamak
Electron Bernstein Wave Heating in the TCV Tokamak A. Mueck 1, Y. Camenen 1, S. Coda 1, L. Curchod 1, T.P. Goodman 1, H.P. Laqua 2, A. Pochelon 1, TCV Team 1 1 Ecole Polytechnique Fédérale de Lausanne
More informationCharacterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment
Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment M.W. Bongard, J.L. Barr, M.G. Burke, R.J. Fonck, E.T. Hinson, J.M. Perry, A.J. Redd, D.J. Schlossberg, K.E. Thome
More informationEffect of the MHD Perturbations on Runaway Beam Formation during Disruptions in the T-10 Tokamak
1 Effect of the MHD Perturbations on Runaway Beam Formation during Disruptions in the T-10 Tokamak P. V. Savrukhin 1), E. V. Popova 1), A. V. Sushkov 1), D. E. Kravtsov 1), S. A. Grashin 1), V. P. Budaev
More information3-D Random Reconnection Model of the Sawtooth Crash
3-D Random Reconnection Model of the Sawtooth Crash Hyeon K. Park Princeton Plasma PhysicsN Laboratory Princeton University at IPELS, 2007 Cairns, Australia August 5-9, 2007 Collaboration with N.C. Luhmann,
More informationControl of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal
Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A. Roberds,
More informationSUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS
SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-1 TOKAMAK PLASMAS V. Vershkov, L.G. Eliseev, S.A. Grashin. A.V. Melnikov, D.A. Shelukhin, S.V. Soldatov, A.O. Urazbaev and T-1 team
More informationFAST 1 : a Physics and Technology Experiment on the Fusion Road Map
Fusion Advanced Studies Torus FAST 1 : a Physics and Technology Experiment on the Fusion Road Map Presented by A. A. Tuccillo on behalf of ENEA-Euratom Association Univ. of Rome Tor Vergata Univ. of Catania
More informationReduction of fluctuations and edge current during PPCD in MST. B. E. Chapman and the MST group
Reduction of fluctuations and edge current during PPCD in MST B. E. Chapman and the MST group Outline -- The key to sustained fluctuation reduction during PPCD -- Magnetic fluctuations (including single
More informationAnalysis 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 information1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator
Max-Planck-Institut für Plasmaphysik 1) H-mode in Helical Devices M. Hirsch 1, T. Akiyama 2, T.Estrada 3, T. Mizuuchi 4, K. Toi 2, C. Hidalgo 3 1 Max-Planck-Institut für Plasmaphysik, EURATOM-Ass., D-17489
More informationS1/2 EX/S, EX/D, EX/W
S1/2 EX/S, EX/D, EX/W S1/2 EX/S - Magnetic Confinement Experiments: Stability 47 papers EX/W - Magnetic Confinement Experiments: Wave plasma interactions, current drive & heating, energetic particles 58
More informationBeam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks
Beam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks by M.A. Van Zeeland 1 M. García-Muñoz 2, W.W. Heidbrink 3, I. Classen 4, R.K. Fisher 1, B. Geiger 2,
More informationNonlinear Simulation of Energetic Particle Modes in JT-60U
TH/P6-7 Nonlinear Simulation of Energetic Particle Modes in JT-6U A.Bierwage,N.Aiba 2, K.Shinohara 2, Y.Todo 3,W.Deng 4,M.Ishikawa 2,G.Matsunaga 2 and M. Yagi Japan Atomic Energy Agency (JAEA), Rokkasho,
More informationM.Osakabe, T.Itoh1, K. Ogawa3,4, M. Isobe1,2, K. Toi1,3, T.Ido1,3, A. Shimizu1, S. Kubo1,3, K.Nagaoka1, Y.Takeiri1,2 and LHD experiment group
5th IAEA-TM on EP September 5-10, 2011 Austin, Texas M.Osakabe, T.Itoh1, K. Ogawa3,4, M. Isobe1,2, K. Toi1,3, T.Ido1,3, A. Shimizu1, S. Kubo1,3, K.Nagaoka1, Y.Takeiri1,2 and LHD experiment group 1National
More information