Real-time Data Fusion for Nuclear Fusion

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

Download "Real-time Data Fusion for Nuclear Fusion"

Transcription

1 Real-time Data Fusion for Nuclear Fusion Chris Rapson R. Fischer, L. Giannone, M. Reich, W. Treutterer & the ASDEX Upgrade Team MPI for Plasma Physics, Garching ASDEX Upgrade This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme -8 under grant agreement No The views and opinions epressed herein do not necessarily reflect those of the European Commission.

2 ydata fusion in daily life ASDEX Upgrade Principle: combine independent measurements to improve parameter estimate hear a bang, turn to look Real-time Data Fusion for Nuclear Fusion /5

3 ydata fusion in daily life ASDEX Upgrade Principle: combine independent measurements to improve parameter estimate hear a bang, turn to look position estimation phones: GPS, WiFi, Accelerometer cars: as above, plus wheel encoders, LIDAR, Sonar, cameras, IR... [ Real-time Data Fusion for Nuclear Fusion /5

4 ydata fusion in daily life ASDEX Upgrade Principle: combine independent measurements to improve parameter estimate hear a bang, turn to look position estimation phones: GPS, WiFi, Accelerometer cars: as above, plus wheel encoders, LIDAR, Sonar, cameras, IR... [ sports refereeing player statistics entertainment [ Real-time Data Fusion for Nuclear Fusion /5

5 ydata fusion in theory A large body of work, applied to many different fields combine two independent measurements E( obs, = σ E( obs σ, = σ σ + σ + σ + σ E( obs σ + σ P( obs P( obs Real-time Data Fusion for Nuclear Fusion 3/5

6 ydata fusion in theory A large body of work, applied to many different fields combine two independent measurements E( obs, = σ E( obs σ, = σ σ + σ + σ + σ E( obs σ + σ P( obs P( obs P( obs, Real-time Data Fusion for Nuclear Fusion 3/5

7 ydata fusion in theory A large body of work, applied to many different fields combine two independent measurements E( obs, = σ E( obs σ, = σ σ + σ + σ + σ E( obs σ + σ P( obs P( obs P( obs, identify and correct systematic errors & drifts if E( obs E( obs, > large error { } fi(obs line integrated density [ 9 m 3 ] 8 #987 DCN H DCN H Thomson time [s] Real-time Data Fusion for Nuclear Fusion 3/5

8 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π obs t,t obs t obs t P( t obs t Real-time Data Fusion for Nuclear Fusion /5

9 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( initial estimate particles true value Real-time Data Fusion for Nuclear Fusion /5

10 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( measured, t= Real-time Data Fusion for Nuclear Fusion /5

11 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( resampled, t= Real-time Data Fusion for Nuclear Fusion /5

12 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( evolved, t= Real-time Data Fusion for Nuclear Fusion /5

13 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( measured, t= Real-time Data Fusion for Nuclear Fusion /5

14 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( resampled, t= Real-time Data Fusion for Nuclear Fusion /5

15 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( evolved, t= Real-time Data Fusion for Nuclear Fusion /5

16 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( measured, t= Real-time Data Fusion for Nuclear Fusion /5

17 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( resampled, t= Real-time Data Fusion for Nuclear Fusion /5

18 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( evolved, t= Real-time Data Fusion for Nuclear Fusion /5

19 ydata fusion in theory We can also include our prior knowledge of the system dynamics Kalman Filter optimal for linear systems with Gaussian noise developed in the 6s flew on the Apollo missions Etended Kalman Filter local linearisation of non-linear systems with Gaussian noise Particle Filter fully non-linear system and noise e.g. linear model ( = +.5 with bimodal measurement (aliasing, mirroring or modulo π P( t obs t obs t obs t obs t,t P( measured, t= Real-time Data Fusion for Nuclear Fusion /5

20 yeisting applications of data fusion in tokamaks Lots of potential because one parameter can be measured in different ways different parameters are linked by common geometry Offline Integrated Data Analysis [Fischer, this conference] Minerva [Svensson 8 PPCF, von Nessi PoP] L/H-mode identification [e.g. Giannone PPCF] Z eff [Verdoolaege IEEE] Real-time [Fischer F Sci Tech, ] RAPTOR [Felici, this conference] disruption prediction [several contributors, this conference] MHD mode number tracking [e.g. Galperti PPCF, Alves 3 PPCF] Real-time Data Fusion for Nuclear Fusion 5/5

21 yntm Stabilisation NTMs decrease confinement and can cause disruptions stabilise or prevent NTMs with localised heating and current drive ECCD Real-time Data Fusion for Nuclear Fusion 6/5

22 yntm Stabilisation NTMs decrease confinement and can cause disruptions stabilise or prevent NTMs with localised heating and current drive ECCD requires accurate targetting: accuracy < w island in AUG, accuracy < cm in ITER, accuracy < 3 cm [Sauter PPCF, La Haye 8 NF] more power required if ECCD deposition is less accurate growth rate dw/dt [ms ]. w marg ECCD off ECCD on w sat. 6 w [cm] NTM w island Real-time Data Fusion for Nuclear Fusion 6/5

23 yntm Stabilisation NTMs decrease confinement and can cause disruptions stabilise or prevent NTMs with localised heating and current drive ECCD requires accurate targetting: accuracy < w island in AUG, accuracy < cm in ITER, accuracy < 3 cm [Sauter PPCF, La Haye 8 NF] more power required if ECCD deposition is less accurate in terms of mirror angle <.. ITER mirrors specified to ±.5 requires accurate localisation growth rate dw/dt [ms ]. w marg ECCD off ECCD on w sat. 6 w [cm] NTM w island Real-time Data Fusion for Nuclear Fusion 6/5

24 yntm Localisation - Method : Equilibrium NTMs only occur at flu surfaces with rational q location of q surfaces can be obtained from equilibrium equilibrium is a pre-requisite for EC ray-tracing calculations + always available, even before NTM appears difficult to diagnose to q profile large uncertainty of flu surface location Real-time Data Fusion for Nuclear Fusion 7/5

25 ASDEX Upgrade yntm Localisation - Method : Te Fluctuations NTM detected as B by Mirnov coils and T e by ECE inversion radius can be associated with an ECE channel (change of correlation phase by π [Reich et al. F Sci Tech. ] ECE channel location is known at the midplane + + low uncertainty in ECE channel identification uncertainty improves for big NTMs some false positives midplane location must be transposed to deposition location reintroduces uncertainty only useful once island eists Real-time Data Fusion for Nuclear Fusion ECRH ECE 8/5

26 yntm Localisation - Method 3: Amplitude ASDEX Upgrade decreases when EC is well aligned + no spatial resolution limitation ρq=.5.6 ρeccd.5 ρtarget. 6 NTM width [au] NTM amplitude is B island width ρ [no units] #967 ep sim time [s] B is a noisy measurement search for min B is non-linear difficult for control amplitude changes can be due to adding or removing NBI power only useful if EC approimately on target only useful once island eists [Humphreys et al. PoP. 6] Real-time Data Fusion for Nuclear Fusion 9/5

27 Equilibrium σ =. ysensor Functions P(NTM pos ρ pol.6.8 T e Fluctuations σ =. weighted by the NTM amplitude Ḃ P(NTM pos ρ pol Amplitude σ =. negative if amplitude increases weighted by + dβ dt one peak for each gyrotron which is within. ρ pol of the q-surface P(NTM pos.. ρ pol.6.8 Real-time Data Fusion for Nuclear Fusion /5

28 ydata Fusion for NTM Localisation use a grid-based filter - like a particle filter without resampling avoids sample impoverishment since NTM can occur anywhere, anytime more computation since more grid points needed for same resolution maintain likelihood estimate for each sensor separately, then add Real-time Data Fusion for Nuclear Fusion /5

29 ydata Fusion for NTM Localisation use a grid-based filter - like a particle filter without resampling avoids sample impoverishment since NTM can occur anywhere, anytime more computation since more grid points needed for same resolution maintain likelihood estimate for each sensor separately, then add instead of normalising every time-step, use a forgetting factor τ forget (mag = τ forget (ECE =. s τ forget (ampl =.7 s time [s] time [s] Real-time Data Fusion for Nuclear Fusion /5

30 ydata Fusion for NTM Localisation use a grid-based filter - like a particle filter without resampling avoids sample impoverishment since NTM can occur anywhere, anytime more computation since more grid points needed for same resolution maintain likelihood estimate for each sensor separately, then add instead of normalising every time-step, use a forgetting factor τ forget (mag = τ forget (ECE =. s τ forget (ampl =.7 s compensate the cumulative effects of a long τ forget with weights w(mag = w(ece = w(ampl = time [s] time [s] Real-time Data Fusion for Nuclear Fusion /5

31 yapply Fused Data to Feedback #357 - test archived data ρ pol.8.6 mag estimate data fus estimate w [cm] ρ ρ NTM pol pol ECE estimate data fus estimate data fus estimate EC 6 time [s] 5 5 Real-time Data Fusion for Nuclear Fusion /5

32 yapply Fused Data to Feedback tracks mag estimate before NTM appears #357 - test archived data ρ pol.8.6 mag estimate data fus estimate w [cm] ρ ρ NTM pol pol ECE estimate data fus estimate data fus estimate EC 6 time [s] 5 5 Real-time Data Fusion for Nuclear Fusion /5

33 yapply Fused Data to Feedback tracks mag estimate before NTM appears tracks ECE estimate when island is large and EC off #357 - test archived data ρ pol ρ pol ECE estimate data fus estimate mag estimate data fus estimate w [cm] ρ NTM pol data fus estimate EC 6 time [s] 5 5 Real-time Data Fusion for Nuclear Fusion /5

34 yapply Fused Data to Feedback tracks mag estimate before NTM appears tracks ECE estimate when island is large and EC off ampl changes show if NTM is at the EC deposition location - or not! #357 - test archived data ρ pol ρ pol ECE estimate data fus estimate mag estimate data fus estimate w [cm] ρ NTM pol data fus estimate EC 6 time [s] 5 5 Real-time Data Fusion for Nuclear Fusion /5

35 yapply Fused Data to Feedback tracks mag estimate before NTM appears tracks ECE estimate when island is large and EC off ampl changes show if NTM is at the EC deposition location - or not! result is better than any of the diagnostics by themselves #357 - test archived data ρ pol ρ pol ρ pol w NTM [cm] ECE estimate data fus estimate mag estimate data fus estimate data fus estimate EC 6 time [s] 5 5 Real-time Data Fusion for Nuclear Fusion /5

36 yapply Fused Data to Feedback tracks mag estimate before NTM appears tracks ECE estimate when island is large and EC off ampl changes show if NTM is at the EC deposition location - or not! result is better than any of the diagnostics by themselves in FB, sweep target around ma likelihood, down to 9% ρ pol ρ pol ρ pol w NTM [cm] #357 - FB simulation NTM mag estimate data fus estimate NTM ECE estimate data fus estimate NTM data fus estimate target EC.5 3 time [s] Real-time Data Fusion for Nuclear Fusion /5

37 yapply Fused Data to Feedback tracks mag estimate before NTM appears tracks ECE estimate when island is large and EC off ampl changes show if NTM is at the EC deposition location - or not! result is better than any of the diagnostics by themselves in FB, sweep target around ma likelihood, down to 9% real-time C ++ version ready to run ρ pol ρ pol ρ pol w NTM [cm] #357 - FB simulation NTM mag estimate data fus estimate NTM ECE estimate data fus estimate NTM data fus estimate target EC.5 3 time [s] Real-time Data Fusion for Nuclear Fusion /5

38 #365 s Equilibria: EQI( Diagnostics: ECE Radiometer ECE Radiometer (-6 yalternative Concepts for Position Control magnetic diagnostics susceptible to drift in long pulse eperiments radiation damage in reactors need alternatives for DEMO the more options the better [Santos NF ] Reflectometry measures n e profiles and can estimate gaps ECE can estimate the separatri position where T e ev take care with shine-through Soft X-Ray can estimate position of ma radiation as proy for z centre Trad [ev] 3 R aus.6.8. R [m] [SXR images courtesy of M. Weiland, to be published] Real-time Data Fusion for Nuclear Fusion 3/5

39 ydata Fusion for Position Control P(R P(R P(R P(R P(R AUG mag refl total ECE model R [m] Real-time Data Fusion for Nuclear Fusion /5

40 ydata Fusion for Position Control P(R P(R P(R P(R P(R AUG mag refl total ECE model R [m] Real-time Data Fusion for Nuclear Fusion /5

41 ydata Fusion for Position Control P(R AUG mag P(R DEMO mag (slow P(R refl P(R refl P(R ECE P(R ECE P(R model P(R model P(R total P(R total R [m] R [m] Real-time Data Fusion for Nuclear Fusion /5

42 yconclusions Data fusion in nuclear fusion mature methods eist potential to eploit these techniques in fusion eperiments - more than we have so far will be vital for diagnostics in a reactor Two eamples shown NTM localisation combining equilibrium, ECE and amplitude performs well in FB simulations ready to test in eperiment plasma position estimation concept involving many diagnostics Real-time Data Fusion for Nuclear Fusion 5/5

Neoclassical Tearing Modes

Neoclassical Tearing Modes Neoclassical Tearing Modes O. Sauter 1, H. Zohm 2 1 CRPP-EPFL, Lausanne, Switzerland 2 Max-Planck-Institut für Plasmaphysik, Garching, Germany Physics of ITER DPG Advanced Physics School 22-26 Sept, 2014,

More information

Introduction to Integrated Data Analysis

Introduction to Integrated Data Analysis 7th Workshop on Fusion Data Processing, Validation and Analysis Introduction to Integrated Data Analysis R. Fischer Max-Planck-Institut für Plasmaphysik, Garching EURATOM Association Frascati, Mar 26-28,

More information

First plasma operation of Wendelstein 7-X

First 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 information

Experiments on Actuator Management and Integrated Control at ASDEX Upgrade

Experiments on Actuator Management and Integrated Control at ASDEX Upgrade EUROFUSION WPMST1-CP(16) 15539 CJ Rapson et al. Experiments on Actuator Management and Integrated Control at ASDEX Upgrade Preprint of Paper to be submitted for publication in Proceedings of 29th Symposium

More information

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform EUROFUSION WPCD-PR(16) 15379 R Coelho et al. Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform Preprint of Paper to be submitted for publication

More information

The performance of improved H-modes at ASDEX Upgrade and projection to ITER

The performance of improved H-modes at ASDEX Upgrade and projection to ITER EX/1-1 The performance of improved H-modes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOM-Association, D-85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy

More information

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal Effects of stellarator transform on sawtooth oscillations in CTH Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, E.C. Howell, C.A. Johnson, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A.

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS 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 information

Turbulence and transport reduction with innovative plasma shapes in TCV - correlation ECE measurements and gyrokinetic simulations

Turbulence and transport reduction with innovative plasma shapes in TCV - correlation ECE measurements and gyrokinetic simulations Turbulence and transport reduction with innovative plasma shapes in TCV - correlation ECE measurements and gyrokinetic simulations A. Pochelon, and the TCV team 1 Ecole Polytechnique de Lausanne (EPFL)

More information

Dutch Nuclear Fusion program

Dutch Nuclear Fusion program Dutch Nuclear Fusion program Marco de Baar DIFFER is part of and A physicist s dream??? International landscape: Roadmap (1) Eurofusion consortium & Nuclear Fusion Roadmap ITER key facility in the roadmap.

More information

Power Balance Analysis of Wendelstein 7-X Plasmas Using Profile Diagnostics

Power Balance Analysis of Wendelstein 7-X Plasmas Using Profile Diagnostics EUROFUSION WPS1-PR(16) 16280 S Bozhenkov et al. Power Balance Analysis of Wendelstein 7-X Plasmas Using Profile Diagnostics Preprint of Paper to be submitted for publication in 43rd European Physical Society

More information

Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal

Control 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 information

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:

More information

and expectations for the future

and expectations for the future 39 th Annual Meeting of the FPA 2018 First operation of the Wendelstein 7-X stellarator and expectations for the future Hans-Stephan Bosch Max-Planck-Institut für Plasmaphysik Greifswald, Germany on behalf

More information

THE DIII D PROGRAM THREE-YEAR PLAN

THE DIII D PROGRAM THREE-YEAR PLAN THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned

More information

The role of stochastization in fast MHD phenomena on ASDEX Upgrade

The 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 information

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

STABILIZATION 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 information

Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator

Influence 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 information

Impact 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 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 information

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Characterization 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 information

Using Bayesian Analysis to Study Tokamak Plasma Equilibrium

Using Bayesian Analysis to Study Tokamak Plasma Equilibrium Using Bayesian Analysis to Study Tokamak Plasma Equilibrium Greg T. von Nessi (joint work with Matthew Hole, Jakob Svensson, Lynton Appel, Boyd Blackwell, John Howard, David Pretty and Jason Bertram) Outline

More information

Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak

Active 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 information

Recent Developments and Applications of Bayesian Data Analysis in Fusion Science: Integrated Data Analysis

Recent Developments and Applications of Bayesian Data Analysis in Fusion Science: Integrated Data Analysis MPI for Extraterrestrial Physics: Bayes Forum Recent Developments and Applications of Bayesian Data Analysis in Fusion Science: Integrated Data Analysis R. Fischer, L. Barrera, A. Burckhart, M.G. Dunne,

More information

MHD Stabilization Analysis in Tokamak with Helical Field

MHD Stabilization Analysis in Tokamak with Helical Field US-Japan Workshop on MHD Control, Magnetic Islands and Rotation the University of Texas, Austin, Texas, USA AT&T Executive Education & Conference Center NOVEMBER 3-5, 8 MHD Stabilization Analysis in Tokamak

More information

Advanced Tokamak Research in JT-60U and JT-60SA

Advanced 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 information

Electron temperature barriers in the RFX-mod experiment

Electron 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 information

A sodium (Na) beam edge diagnostic

A sodium (Na) beam edge diagnostic P2-39 A sodium (Na) beam edge diagnostic E.Wolfrum a*, J. Schweinzer a, D. Bridi b, K. Igenbergs b, J. Kamleitner b, F. Aumayr b and the ASDEX Upgrade Team a a Max Planck Institut für Plasmaphysik, EURATOM

More information

Performance limits. Ben Dudson. 24 th February Department of Physics, University of York, Heslington, York YO10 5DD, UK

Performance 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 information

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas 1 PD/1-1 First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas R. Nazikian 1, W. Suttrop 2, A. Kirk 3, M. Cavedon 2, T.E. Evans

More information

Effect of rotational transform and magnetic shear on confinement of stellarators

Effect of rotational transform and magnetic shear on confinement of stellarators Effect of rotational transform and magnetic shear on confinement of stellarators E. Ascasíbar(1), D. López-Bruna(1), F. Castejón(1), V.I. Vargas(1), V. Tribaldos(1), H. Maassberg(2), C.D. Beidler(2) R.

More information

Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate

Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate Contract for the Operation of the JET Facilities Co-Funded by Euratom NJOC-CP(16) 15392 A Shepherd et al. Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate Preprint

More information

Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport

Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport EUROFUSION WPJET1-PR(16) 15411 TJJ Tala et al. Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport Preprint of Paper to be submitted for publication in 43rd European Physical

More information

Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas

Resistive 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 information

Magnetic Flux Surface Measurements at Wendelstein 7-X

Magnetic Flux Surface Measurements at Wendelstein 7-X EUROFUSION WPS1-PR(16) 15578 M. Otte et al. Magnetic Flux Surface Measurements at Wendelstein 7-X Preprint of Paper to be submitted for publication in 43rd European Physical Society Conference on Plasma

More information

First Experiments Testing the Working Hypothesis in HSX:

First 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 information

INTERNATIONAL ATOMIC ENERGY AGENCY 21 st IAEA Fusion Energy Conference Chengdu, China, October 2006

INTERNATIONAL ATOMIC ENERGY AGENCY 21 st IAEA Fusion Energy Conference Chengdu, China, October 2006 IAEA INTERNATIONAL ATOMIC ENERGY AGENCY st IAEA Fusion Energy Conference Chengdu, China, 6 - October 6 IAEA-CN-9/EX/- THE PERFORMANCE OF IMPROVED H-MODES AT ASDEX UPGRADE AND PROJECTION TO A.C.C. SIPS,

More information

The emissivity of W coatings deposited on carbon materials for fusion applications

The emissivity of W coatings deposited on carbon materials for fusion applications EUROFUSION WPJET2-CP(16) 15583 C Ruset et al. The emissivity of W coatings deposited on carbon materials for fusion applications Preprint of Paper to be submitted for publication in Proceedings of 29th

More information

Development in DIII D Tokamak Hybrid Operation Scenarios

Development in DIII D Tokamak Hybrid Operation Scenarios Development in Tokamak Hybrid Operation Scenarios by R.J. Jayakumar in collaboration with M.R. Wade, T.C. Luce, P.A. Politzer, A.W. Hyatt, J.R. Ferron, C.M. Greenfield, E.H. Joffrin, M. Murakami, C.C.

More information

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.

More information

Observation of modes at frequencies above the Alfvén frequency in JET

Observation 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 information

Sawtooth Control. J. P. Graves CRPP, EPFL, Switzerland. FOM Instituut voor Plasmafysica Rijnhuizen, Association EURATOM-FOM, The Netherlands

Sawtooth Control. J. P. Graves CRPP, EPFL, Switzerland. FOM Instituut voor Plasmafysica Rijnhuizen, Association EURATOM-FOM, The Netherlands Sawtooth Control J. P. Graves CRPP, EPFL, Switzerland B. Alper 1, I. Chapman 2, S. Coda, M. de Baar 3, L.-G. Eriksson 4, R. Felton 1, D. Howell 2, T. Johnson 5, V. Kiptily 1, R. Koslowski 6, M. Lennholm

More information

Temporal Evolution of Temperature and Argon Impurity Density Profiles Observed by X-ray Imaging Spectrometer Measurements at Wendelstein 7-X

Temporal Evolution of Temperature and Argon Impurity Density Profiles Observed by X-ray Imaging Spectrometer Measurements at Wendelstein 7-X EUROFUSION WPS1-PR(16) 15653 A. Langenberg et al. Temporal Evolution of Temperature and Argon Impurity Density Profiles Observed by X-ray Imaging Spectrometer Measurements at Wendelstein 7-X Preprint of

More information

Introduction to Fusion Physics

Introduction to Fusion Physics Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction

More information

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment. Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment E. Kolemen a, S.L. Allen b, B.D. Bray c, M.E. Fenstermacher b, D.A. Humphreys c, A.W. Hyatt c, C.J. Lasnier b,

More information

A Faster Way to Fusion

A Faster Way to Fusion A Faster Way to Fusion 2017 Tokamak Energy Tokamak Energy Ltd Company Overview April 2018 Our Mission To deliver to mankind a cheap, safe, secure and practically limitless source of clean energy fusion

More information

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén Current density modelling in JET and JT-60U identity plasma experiments Paula Sirén 1/12 1/16 Euratom-TEKES Euratom-Tekes Annual Seminar 2013 28 24 May 2013 Paula Sirén Current density modelling in JET

More information

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST CCFE-PR(13)33 J. R. Harrison, G. M. Fishpool and A. Kirk L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST Enquiries about copyright and reproduction should in the first instance

More information

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139 Alcator C-Mod Double Transport Barrier Plasmas in Alcator C-Mod J.E. Rice for the C-Mod Group MIT PSFC, Cambridge, MA 139 IAEA Lyon, Oct. 17, Outline Double Barrier Plasma Profiles and Modeling Conditions

More information

Introduction to the Diagnosis of Magnetically Confined Thermonuclear Plasma

Introduction to the Diagnosis of Magnetically Confined Thermonuclear Plasma Introduction to the Diagnosis of Magnetically Confined Thermonuclear Plasma Core diagnostics II: Bolometry and Soft X-rays J. Arturo Alonso Laboratorio Nacional de Fusión EURATOM-CIEMAT E6 P2.10 arturo.alonso@ciemat.es

More information

EUROFUSION WPJET1-PR(16) CG Albert et al.

EUROFUSION WPJET1-PR(16) CG Albert et al. EUROFUSION WPJET1-PR(16) 15331 CG Albert et al. Hamiltonian approach for evaluation of toroidal torque from finite amplitude non-axisymmetric perturbations of a tokamak magnetic field in resonant transport

More information

Integrated Modelling of ITER Scenarios with ECCD

Integrated Modelling of ITER Scenarios with ECCD Integrated Modelling of ITER Scenarios with ECCD J.F. Artaud, V. Basiuk, J. Garcia, G. Giruzzi*, F. Imbeaux, M. Schneider Association Euratom-CEA sur la Fusion, CEA/DSM/DRFC, CEA/Cadarache, 13108 St. Paul-lez-Durance,

More information

Determination of q Profiles in JET by Consistency of Motional Stark Effect and MHD Mode Localization

Determination of q Profiles in JET by Consistency of Motional Stark Effect and MHD Mode Localization Determination of q Profiles in JET by Consistency of Motional Stark Effect and MHD Mode Localization R. De Angelis 1), F. Orsitto1), M. Baruzzo 2), P. Buratti 1), B. Alper 3), L. Barrera 4), A. Botrugno

More information

MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade

MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade EUROFUSION WPMST1-CP(16) 15178 V Igochine et al. MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade Preprint of Paper to be submitted for publication in Proceedings of 26th

More information

Role of Magnetic Configuration and Heating Power in ITB Formation in JET.

Role 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 information

ENEA for EUROfusion, via E. Fermi 45, Frascati (Rome), Italy 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, , China 3

ENEA for EUROfusion, via E. Fermi 45, Frascati (Rome), Italy 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, , China 3 Quasi-Snowflake divertor studies on EAST G. Calabrò 1, B.J. Xiao 2,3, S. L. Chen 2, Y.M. Duan 2, Y. Guo 2, J.G. Li 2, L. Liu 2, Z.P. Luo 2, L. Wang 2, J. Xu 2, B. Zhang 2, R. Albanese 4, R. Ambrosino 4,

More information

Effect of ideal kink instabilities on particle redistribution

Effect 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 information

C-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 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 information

Active MHD Control Needs in Helical Configurations

Active 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 information

Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research

Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research 1 TH/P9-10 Three Dimensional Effects in Tokamaks How Tokamaks Can Benefit From Stellarator Research S. Günter, M. Garcia-Munoz, K. Lackner, Ph. Lauber, P. Merkel, M. Sempf, E. Strumberger, D. Tekle and

More information

Performance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges

Performance, 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 information

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code Contrib. Plasma Phys. 56, No. 6-8, 772 777 (2016) / DOI 10.1002/ctpp.201610008 Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code K. Gała zka 1, I. Ivanova-Stanik 1, M. Bernert 2, A. Czarnecka

More information

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas D. Borba 1,9, R. Nazikian 2, B. Alper 3, H.L. Berk 4, A. Boboc 3, R.V. Budny 2, K.H. Burrell 5, M. De Baar

More information

Application of the ECRH radiation for plasma diagnostics in Wendelstein 7-X

Application of the ECRH radiation for plasma diagnostics in Wendelstein 7-X EUROFUSION WPS1-CP(16) 15150 D Moseev et al. Application of the ECRH radiation for plasma diagnostics in Wendelstein 7-X Preprint of Paper to be submitted for publication in Proceedings of 26th IAEA Fusion

More information

Recent 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 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 information

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation - 15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect

More information

THE ADVANCED TOKAMAK DIVERTOR

THE ADVANCED TOKAMAK DIVERTOR I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and

More information

Snakes and similar coherent structures in tokamaks

Snakes and similar coherent structures in tokamaks Snakes and similar coherent structures in tokamaks A. Y. Aydemir 1, K. C. Shaing 2, and F. W. Waelbroeck 1 1 Institute for Fusion Studies, The University of Texas at Austin, Austin, TX 78712 2 Plasma and

More information

Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER

Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER 2267-1 Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics 3-14 October 2011 Introduction to Fusion Leading to ITER SNIPES Joseph Allan Directorate for Plasma Operation Plasma Operations

More information

Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor

Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor M. Kikuchi, T. Takizuka, S. Medvedev, T. Ando, D. Chen, J.X. Li, M. Austin, O. Sauter, L. Villard, A.

More information

Mitigation of ELMs and Disruptions by Pellet Injection

Mitigation of ELMs and Disruptions by Pellet Injection TH/P4-5 Mitigation of ELMs and Disruptions by Pellet Injection K. Gál ), T. Fehér ), T. Fülöp ), P. T. Lang 3), H. M. Smith 4), ASDEX Upgrade Team 5) and JET-EFDA contributors 3) ) KFKI-RMKI, Association

More information

Progressing 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 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 information

for the French fusion programme

for the French fusion programme The ITER era : the 10 year roadmap for the French fusion programme E. Tsitrone 1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France Association EURATOM-CEA TORE

More information

Plasma response of magnetic perturbation at the edge: Comparisons between measurements and 3D MHD models

Plasma response of magnetic perturbation at the edge: Comparisons between measurements and 3D MHD models EUROFUSION WPMST1-CP(16) 15057 M Willensdorfer et al. Plasma response of magnetic perturbation at the edge: Comparisons between measurements and 3D MHD models Preprint of Paper to be submitted for publication

More information

Plasma Response Control Using Advanced Feedback Techniques

Plasma Response Control Using Advanced Feedback Techniques Plasma Response Control Using Advanced Feedback Techniques by M. Clement 1 with J. M. Hanson 1, J. Bialek 1 and G. A. Navratil 1 1 Columbia University Presented at 59 th Annual APS Meeting Division of

More information

SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS

SUMMARY 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 information

Spatio-temporal investigations on the triggering of pellet induced ELMs

Spatio-temporal investigations on the triggering of pellet induced ELMs Spatio-temporal investigations on the triggering of pellet induced ELMs G. Kocsis, S. Kálvin, P.T. Lang*, M. Maraschek*, J. Neuhauser* W. Schneider*, T. Szepesi and ASDEX Upgrade Team KFKI-RMKI, EURATOM

More information

Impact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas

Impact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas 1 P/233 Impact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas D. Frigione 1, M. Romanelli 2, C. Challis 2, J. Citrin 3, L. Frassinetti 4, J. Graves 5, J. Hobirk 6, F. Koechl 2, M.

More information

Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter

Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Matthias Hölzl Nonlinear ELM Simulations DPG Spring Meeting, Jena, 02/2013

More information

Transport and turbulence reduction with negative triangularity : Correlation ECE measurements in TCV

Transport and turbulence reduction with negative triangularity : Correlation ECE measurements in TCV Transport and turbulence reduction with negative triangularity : Correlation ECE measurements in TCV A. Pochelon, M.Rancic, V.S.Udintsev 1, T.P.Goodman, E.Fable 2, B.Labit, O.Sauter, R.Behn, A.Bottino

More information

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER D. BOUCHER 1, D. MOREAU 2, G. VAYAKIS 1, I. VOITSEKHOVITCH 3, J.M. ANÉ 2, X. GARBET 2, V. GRANDGIRARD 2, X. LITAUDON 2, B. LLOYD

More information

Electron Bernstein Wave Heating in the TCV Tokamak

Electron 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 information

PHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China.

PHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China. PHYSICS OF CFETR Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China Dec 4, 2013 Mission of CFETR Complementary with ITER Demonstration of fusion

More information

Diagnostics for Burning Plasma Physics Studies: A Status Report.

Diagnostics 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 information

2D ECE measurements of type-i Edge Localized Modes at ASDEX Upgrade

2D ECE measurements of type-i Edge Localized Modes at ASDEX Upgrade 2D ECE measurements of type-i Edge Localized Modes at ASDEX Upgrade J E Boom 1, I G J Classen 1, P C de Vries 1, T Eich 2, E Wolfrum 2, W Suttrop 2, R P Wenninger 3, A J H Donné 1,4, B J Tobias 5, C W

More information

On tokamak plasma rotation without the neutral beam torque

On 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 information

MHD Induced Fast-Ion Losses in ASDEX Upgrade

MHD Induced Fast-Ion Losses in ASDEX Upgrade Max-Planck-Insititut für Plasmaphysik MHD Induced Fast-Ion Losses in ASDEX Upgrade Manuel García-Muñoz1 H.-U. Fahrbach1, M. Bruedgam1, V. Bobkov1, A. Flaws1, M. Gobbin2, S. Günter1, P. Lauber1, M. Mantsinen1,4,

More information

Non-linear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade

Non-linear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade 1 TH/P1-26 Non-linear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade F.Orain 1, M.Hölzl 1, E.Viezzer 1, M.Dunne 1, M.Bécoulet 2, P.Cahyna 3, G.T.A.Huijsmans

More information

Characteristics of the H-mode H and Extrapolation to ITER

Characteristics of the H-mode H and Extrapolation to ITER Characteristics of the H-mode H Pedestal and Extrapolation to ITER The H-mode Pedestal Study Group of the International Tokamak Physics Activity presented by T.Osborne 19th IAEA Fusion Energy Conference

More information

MHD instability driven by supra-thermal electrons in TJ-II stellarator

MHD 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 information

Non-local Models of Perturbative Transport: Numerical Results and Application to JET Experiments

Non-local Models of Perturbative Transport: Numerical Results and Application to JET Experiments 1 TH/P8-38 Non-local Models of Perturbative Transport: Numerical Results and Application to JET Eperiments D.del-Castillo-Negrete 1, P.Mantica 2, V.Naulin 3, J.J. Rasmussen 3 and JET EFDA contributors

More information

The non-resonant kink modes triggering strong sawtooth-like crashes. in the EAST tokamak. and L. Hu 1

The non-resonant kink modes triggering strong sawtooth-like crashes. in the EAST tokamak. and L. Hu 1 The non-resonant kink modes triggering strong sawtooth-like crashes in the EAST tokamak Erzhong Li 1, V. Igochine 2, O. Dumbrajs 3, L. Xu 1, K. Chen 1, T. Shi 1, and L. Hu 1 1 Institute of Plasma Physics,

More information

Edge Zonal Flows and Blob Propagation in Alcator C-Mod P5.073 EPS 2011

Edge Zonal Flows and Blob Propagation in Alcator C-Mod P5.073 EPS 2011 Edge Zonal Flows and Blob Propagation in Alcator C-Mod S.J. Zweben 1, J.L. Terry 2, M. Agostini 3, B. Davis 1, O. Grulke 4,J. Hughes 2, B. LaBombard 2 D.A. D'Ippolito 6, R. Hager 5, J.R. Myra 6, D.A. Russell

More information

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET P1-3 L. Aho-Mantila a *, M. Bernert b, J.W. Coenen c, R. Fischer b, M. Lehnen c, C. Lowry d, S. Marsen e, K. McCormick

More information

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy)

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Bolometry H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Revised May 28, 2002 1. Radiated power Time and space resolved measurements of the total plasma radiation can be done by means

More information

0 Magnetically Confined Plasma

0 Magnetically Confined Plasma 0 Magnetically Confined Plasma 0.1 Particle Motion in Prescribed Fields The equation of motion for species s (= e, i) is written as d v ( s m s dt = q s E + vs B). The motion in a constant magnetic field

More information

Tungsten: An option for divertor and main chamber PFCs in future fusion devices

Tungsten: An option for divertor and main chamber PFCs in future fusion devices ASDEX Upgrade Tungsten: An option for divertor and main chamber PFCs in future fusion devices R. Neu, R. Dux, A. Kallenbach, C.F. Maggi, T. Pütterich, M. Balden, T. Eich, J.C. Fuchs, O. Gruber, A. Herrmann,

More information

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory

Localized 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 information

A New Resistive Response to 3-D Fields in Low Rotation H-modes

A New Resistive Response to 3-D Fields in Low Rotation H-modes in Low Rotation H-modes by Richard Buttery 1 with Rob La Haye 1, Yueqiang Liu 2, Bob Pinsker 1, Jong-kyu Park 3, Holger Reimerdes 4, Ted Strait 1, and the DIII-D research team. 1 General Atomics, USA 2

More information

Dimensionless pedestal identity plasmas on Alcator C-Mod C

Dimensionless pedestal identity plasmas on Alcator C-Mod C Dimensionless pedestal identity plasmas on Alcator C-Mod C and JET G P Maddison 1, A E Hubbard 2, J W Hughes 2, I M Nunes 3, M N A Beurskens 1, S K Erents 1, Pasqualotto 4, E Giovannozzi 5, A Alfier 4,

More information

Controlling Sawtooth Oscillations in Tokamak Plasmas

Controlling Sawtooth Oscillations in Tokamak Plasmas Controlling Sawtooth Oscillations in Tokamak Plasmas IT Chapman EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, United Kingdom E-mail: ian.chapman@ccfe.ac.uk Abstract.

More information