IEA RFP Workshop, April 26-28 2010 Padova Internal electron transport barriers in RFX-mod helical equilibria R. Lorenzini on behalf of the RFX-mod team.

Slides:



Advertisements
Similar presentations
Statistical Properties of Broadband Magnetic Turbulence in the Reversed Field Pinch John Sarff D. Craig, L. Frassinetti 1, L. Marrelli 1, P. Martin 1,
Advertisements

Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Multiple reconnections and explosive events and in MST and solar flares Gennady Fiksel CMSO workshop, Princeton, NJ, Oct 5-8, 2005.
Ideas for overseas contributions to CMSO Piero Martin Consorzio RFX Associazione Euratom-ENEA sulla fusione And Physics Dept., Univ. of Padova, Italy CMSO.
Simulations of the core/SOL transition of a tokamak plasma Frederic Schwander,Ph. Ghendrih, Y. Sarazin IRFM/CEA Cadarache G. Ciraolo, E. Serre, L. Isoardi,
M. Zuin RFX ws 2011 Padova, 7-9/2/2011 Innovative contributions to confinement understanding M. Zuin.
West Lake International Symposium on Plasma Simulation; April, 2012 Influence of magnetic configuration on kinetic damping of the resistive wall.
TAE-EP Interaction in ARIES ACT-I K. Ghantous, N.N Gorelenkov PPPL ARIES Project Meeting,, 26 Sept
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
RFP Workshop, Stockholm 9-11 /10/ 2008 Numerical studies of particle transport mechanisms in RFX-mod low chaos regimes M.Gobbin, L.Marrelli, L.Carraro,
Momentum transport and flow shear suppression of turbulence in tokamaks Michael Barnes University of Oxford Culham Centre for Fusion Energy Michael Barnes.
1 Global Gyrokinetic Simulations of Toroidal ETG Mode in Reversed Shear Tokamaks Y. Idomura, S. Tokuda, and Y. Kishimoto Y. Idomura 1), S. Tokuda 1), and.
MHD Behaviour of Low-Aspect-Ratio RFP Plasmas in RELAX S.Masamune, T.Onchi, A.Sanpei, R.Ikezoe, K.Oki, T.Yamashita, H.Shimazu, N.Nishino 1), R.Paccagnella.
Physics of fusion power Lecture 4: Cylindrical concepts.
13th IEA/RFP Workshop – Stockholm October 9-11, D characterization of thermal core topology changes in controlled RFX-mod QSH states A. Alfier on.
GTC Status: Physics Capabilities & Recent Applications Y. Xiao for GTC team UC Irvine.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
M. Zuin 13th IEA/RFP WorkshopStockholm, October 9-11, 2008 Self-organized helical equilibria emerging at high current in RFX-mod Matteo Zuin on behalf.
S.C. Guo 13th IEA/RFP Workshop, October 9-11, 2008, Stockholm 1 Experiments and modeling on active RWM rotation in RFP plasmas S.C. Guo, M. Baruzzo, T.
RFX-mod Workshop – Padova, January Experimental QSH confinement and transport Fulvio Auriemma on behalf of RFX-mod team Consorzio RFX, Euratom-ENEA.
RFX-mod 2009 programme Workshop, January 20-22, 2009 Report on experimental proposals submitted to TF1 ‘RFP performance: high current operation and advanced.
6 th Japan-Korea Workshop on Theory and Simulation of Magnetic Fusion Plasmas Hyunsun Han, G. Park, Sumin Yi, and J.Y. Kim 3D MHD SIMULATIONS.
Challenges in RFP physics D.F. Escande UMR 6633 CNRS/Aix-Marseille Université, France & Consorzio RFX, Padova, Italy Thanks to D. Bonfiglio, F. Sattin,
14 th IEA-RFP Workshop, Padova 26 th -28 th April 2010 The SHEq code: an equilibrium calculation tool for SHAx states Emilio Martines, Barbara Momo Consorzio.
Calculations of Gyrokinetic Microturbulence and Transport for NSTX and C-MOD H-modes Martha Redi Princeton Plasma Physics Laboratory Transport Task Force.
Challenging problems in kinetic simulation of turbulence and transport in tokamaks Yang Chen Center for Integrated Plasma Studies University of Colorado.
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
Plasma Dynamics Lab HIBP E ~ 0 V/m in Locked Discharges Average potential ~ 580 V  ~ V less than in standard rotating plasmas Drop in potential.
O. Sauter Effects of plasma shaping on MHD and electron heat conductivity; impact on alpha electron heating O. Sauter for the TCV team Ecole Polytechnique.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Internal Transport Barriers and Improved Confinement in Tokamaks (Three possible.
Stellarator tools for neoclassical transport and flow interpretation in helical RFP plasmas M. Gobbin RFX-mod Programme Workshop 2011, February 7-9, Padova,
11 Role of Non-resonant Modes in Zonal Flows and Intrinsic Rotation Generation Role of Non-resonant Modes in Zonal Flows and Intrinsic Rotation Generation.
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
European Ph.D. course. - Garching )p.martin Piero Martin Consorzio RFX- Associazione Euratom-ENEA sulla fusione, Padova, Italy Department of Physics,
Dynamics of ITG driven turbulence in the presence of a large spatial scale vortex flow Zheng-Xiong Wang, 1 J. Q. Li, 1 J. Q. Dong, 2 and Y. Kishimoto 1.
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
QSH/SHAx states: towards the determination of an helical equilibrium L. Marrelli acknowledging fruitful discussions with S.Cappello, T.Bolzonella, D.Bonfiglio,
M. Onofri, F. Malara, P. Veltri Compressible magnetohydrodynamics simulations of the RFP with anisotropic thermal conductivity Dipartimento di Fisica,
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
RFP equilibrium 3. The reversed field pinch magnetic equilibrium ORNL Colloquium – September 10th, 2009.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Challenges for Fusion Theory and Explosive Behaviour in Plasmas Steve Cowley,
Weixing Ding University of California, Los Angeles,USA collaborators: D.L. Brower, W. Bergerson, D. Craig, D. Demers, G.Fiksel, D.J. Den Hartog, J. Reusch,
MCZ 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,
RFX-mod Workshop, Padova 20-22/01/ 2009 Transport in the Helical Core of the RFP M.Gobbin, G.Spizzo, L.Marrelli, L.Carraro, R.Lorenzini, D.Terranova and.
1 Feature of Energy Transport in NSTX plasma Siye Ding under instruction of Stanley Kaye 05/04/09.
T. Bolzonella – 9 February 2011 – RFX-mod programme workshop TF1: Physics integration for high performance RFP Proposals and discussion T. Bolzonella,
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
Transition to helical RFP state and associated change in magnetic stochasticity in a low-aspect-ratio RFP A.Sanpei, R.Ikezoe, T. Onchi, K.Oki, T.Yamashita,
The Joint Meeting of 4th IAEA Technical Meeting on Spherical Tori and 14th International Workshop on Spherical TorusFrascati, 7 to 10 October Ideal.
Role of thermal instabilities and anomalous transport in the density limit M.Z.Tokar, F.A.Kelly, Y.Liang, X.Loozen Institut für Plasmaphysik, Forschungszentrum.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
21st IAEA Fusion Energy Conf. Chengdu, China, Oct.16-21, /17 Gyrokinetic Theory and Simulation of Zonal Flows and Turbulence in Helical Systems T.-H.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
Interaction between vortex flow and microturbulence Zheng-Xiong Wang (王正汹) Dalian University of Technology, Dalian, China West Lake International Symposium.
HT-7 Proposal of the investigation on the m=1 mode oscillations in LHCD Plasmas on HT-7 Exp2005 ASIPP Youwen Sun, Baonian Wan and the MHD Team Institute.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
25 th IAEA Fusion Energy Conference, St. Petersburg 2014 M. E. Puiatti 25 th IAEA Fusion Energy Conference, St. Petersburg 2014 Overview of the RFX-mod.
Neoclassical Predictions of ‘Electron Root’ Plasmas at HSX
Mechanisms for losses during Edge Localised modes (ELMs)
An overview of turbulent transport in tokamaks
Huishan Cai, Jintao Cao, Ding Li
Three-Dimensional MHD Analysis of Heliotron Plasma with RMP
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
Influence of energetic ions on neoclassical tearing modes
T. Morisaki1,3 and the LHD Experiment Group
T. Morisaki1,3 and the LHD Experiment Group
Presentation transcript:

IEA RFP Workshop, April Padova Internal electron transport barriers in RFX-mod helical equilibria R. Lorenzini on behalf of the RFX-mod team Consorzio RFX, Euratom-ENEA Association, Padova, Italy

IEA RFP Workshop, April Padova Outline of the talk  New analyses on the electron Internal Transport Barriers e-ITBS observed in reversed field pinch experiment RFX-mod  These analyses are the result of a joint effort of theory, modelling and data analyses aimed at understanding the role of MHD and microturbulence in driving the transport on the barrier

IEA RFP Workshop, April Padova The RFX-mod experiment RFX-mod (Padua, Italy) is the largest RFP presently in operation (R 0 = 2 m, a = 0.46 m ) RFX-mod has two unique features: – the possibility of reaching Ip up to 2MA – the most advanced feedback coil system ever realized in a fusion device 4×48=192 feedback saddle coils independently controlled and respective sensors

IEA RFP Workshop, April Padova Evidence of a self organized helical plasma When the current increases the amplitude of the innermost resonant mode (m=1, n = -7) increases and eventually saturates while the secondary modes decrease. [P. Piovesan et al., NF 49, (2009)] Long lasting Quasi Single Helicity (QSH) states are routinely observed at I > 1MA. The plasma dithers between QSH and MH (Multiple Helicity) state (all the modes have a comparable amplitude), but QSH phases become more frequent, longer and purer increasing I p 10  E Theory and 3D MHD codes describe a helical ohmic equilibrium self-sustained by a single mode. This is the chaos-free Single Helicity ( SH ) state. [S. Cappello et al., PPCF 46 B313 (2004)

IEA RFP Workshop, April Padova A new magnetic topology: the SHAx When the amplitude of the dominant is large enough the magnetic topology has a Single Magnetic Axis (SHAx) SHAx states are known to be resilient to the magnetic chaos [D. F. Escande et al., PRL. 85, 3169 (2000)] In the SHAx we observe the onset of an electron internal transport barrier (e-ITBs) surrounding a large fraction of the plasma volume. [R. Lorenzini et al., PRL 101, (2008)]

IEA RFP Workshop, April Padova The e-ITBs are helically shaped The magnetic topology of a SHAx is well described in terms of the helical flux  mn (m=1,n=7)  mn =m  0 - nF 0 + (m  mn – nf mn ) exp i(m  -n  ) Analogous conclusion holds [R. Lorenzini et al., Nature Phys. 5, 570 (2009)] :  for soft X-ray measurements  electron density when significant gradients are induced in the core thanks to pellet injection T e is a function of  mn Axisymmetric fieldDominant mode

IEA RFP Workshop, April Padova Fascinating and challenging questions to be answered: 1) do MHD secondary modes play a role in the transport through the e-ITB ? 3) why is T e flat in the core ? 2) if yes, are the MHD instabilities the only drive of transport through the e-ITB ?

IEA RFP Workshop, April Padova do MHD secondary modes play a role in the transport through the e-ITB? When the plasma enters the SHAx state electron temperature and density become functions of the helical flux the flux surfaces are only weakly perturbed by the magnetic chaos and become broken KAM surfaces (cantori), which can sustain strong temperature gradients [S.R. Hudson et al., PRL 100, (2008)] This led us to infer that the flux surfaces are only weakly perturbed by the magnetic chaos and become broken KAM surfaces (cantori), which can sustain strong temperature gradients [S.R. Hudson et al., PRL 100, (2008)] Question 1

IEA RFP Workshop, April Padova... and to lowest s calculated with ASTRA in the static (i.e. power balance) analysis 1) MHD secondary modes play a role The ‘strength’ of the barrier is quantified by means of the gradient length L Te in the barrier: Shortest L Te s are achieved at lowest amplitudes of secondary MHD modes... [R. Lorenzini et al, to be submitted] ><... lowest values of are achieved at lowest values of b ,sec

IEA RFP Workshop, April Padova are the MHD instabilities the only drive of transport through the barrier? Question 2 According to the experience of the other configurations strong gradients are reservoirs of free energy which can trigger microinstabilities These microinstabilities enhance the local transport and damp the increase of temperature Are the e-ITB gradients ‘limited’ ?

IEA RFP Workshop, April Padova... L Te has a lower limit L Te,c ~ 0.2 m 2) Evidence of a ‘critical’ gradient length L Te shows a saturation of the minimum achieved value… a gradient length driven transport mechanism These results suggest the presence of a gradient length driven transport mechanism L Te,c ~ 0.2 m

IEA RFP Workshop, April Padova 2) ITG are stable but... In tokamaks electrostatic Ion Temperature Gradient (ITG) are a major instability and the main cause of transport However several studies agreed that present-days RFX profiles are sub-critical for triggering of ITG [S. C. Guo, PoP 15, (2008), I. Predebon et al., PoP 17, (2010), F. Sattin et al., submitted ] Another class of instabilities are the high-wavenumber MicroTearing (MT) modes : these modes are driven linearly unstable by electron temperature gradients The linear stability of MT in SHAx states has been investigated by means of the gyrokinetic code GS2 adapted to RFP geometry

IEA RFP Workshop, April Padova 2)... MT are unstable! The simulations shows that MT are unstable for a significant range of wavenumbers on the barrier [ I. Predebon et al., to be submitted] A scan in a parameter range relevant for RFX-mod shows that a growth rate  > 0 is found when a/L Te,loc > 2, namely when L Te,loc < 0.2 m ~ L Te,c ~ a/L te,loc

IEA RFP Workshop, April Padova A reduction of stochastic transport is expected Question 3 why is T e flat in the core ? Despite the presence of secondary modes, field line tracing codes (FLiT, ORBIT…) reconstruct surfaces nearly conserved in the plasma core, where the Te profile is flat. However, since there is a significant deposited ohmic power,  is very high and diverges Is this the signature of a non diffusive transport mechanism ? A ‘toy’ model is used to study the electrostatic effects

IEA RFP Workshop, April Padova A mixing mechanism flattens the profile The numerical model solves the Braginskii Equations An ‘elliptical’ domain mimics the ‘bean’ shape of a SHAx An effective diffusivity, which takes into account the stochastic transport, is added to the BE, low in the core and high at the border of the domain SHAx region (low chaos)  profile  Li [ F. Sattin et al., to be submitted] The simulations show the onset of a compressible flow  which, as a mixing mechanism, flattens the Te profile in the low  region time x  L,i )

IEA RFP Workshop, April Padova How to include this model in a transport code The imposed  fits the  PB up to the middle of the barrier, then it is decreased to ~ 1m 2 s -1 Heat flux is parametrized as a conductive + a convective term Q =-n  T+nT V pinch Astra integrates the heat continuity equation up to the convergence The T e profile is flat in the core

IEA RFP Workshop, April Padova Conclusions  Many efforts are devoted to understand the transport through the e-ITBs  The picture we have is that the Te gradients develop thanks to the increased resilience of the SHAx topology to magnetic chaos induced to secondary MHD mode  A residual magnetic chaos due to MHD modes is still present, since steepest gradients and lowest transport are found when secondary modes are lowest  The simulations show that the MTs are unstable on the barrier and could be responsible of the limit on the gradient steepness  Modelling results suggest that the flattening of T e in the core can be due to the presence of a flow generated by electrostatic turbulence

IEA RFP Workshop, April Padova

The role of the magnetic shear

IEA RFP Workshop, April Padova The role of flow Passive spectroscopy reveals correlation between poloidal flow and dominant mode.

IEA RFP Workshop, April Padova What do we need for electrostatic transport? electron energy transport with ohmic source conservation and motion of matter charge unbalance arises electric fields drifts. Hence, we must compute self-consistent electric field The numerical model solves the Braginskii equations: electrons and ions do not move alike +

IEA RFP Workshop, April Padova What do we need for electrostatic transport? The numerical model solves the Braginskii Equations conservation of density An ‘elliptical’ domain mimics the ‘bean’ shape of a SHAx A ‘magnetic’ diffusivity is added to the BE, low in the core and high at the border of the domain conservation of motion for ions and electrons electrons and ions do not move alike charge unbalance arises electric fields drifts conservation of charge heat continuity equation with a ohmic source SHAx region (low chaos)  profile  Li

IEA RFP Workshop, April Padova Evidence of a ‘critical’ gradient length The ‘strength’ of the barrier is quantified by means of the gradient length L Te in the barrier: T top is T e averaged in the core region surrounded by the barrier <> means the average in the region of the barrier

IEA RFP Workshop, April Padova Evidence of a ‘critical’ gradient length... experimentally the gradient length L Te has a lower limit L Te,c ~ 0.2 m Te shows a linear dependence from T top. This dependence, if read in terms of gradient length L Te, means that... a gradient length driven transport mechanism This result indicates that we are in presence of a gradient length driven transport mechanism

IEA RFP Workshop, April Padova A compressible flow flattens T e The simulations show the onset of a compressible flow [ F. Sattin et al.,to be submitted] which, as a mixing mechanism, flattens the T e profile in the low  region

IEA RFP Workshop, April Padova The plasma likes to be helical The synergistic scaling of the dominant and of secondary modes makes the QSH be purer The spectral index N S =1 in Single Helicity condition The plasma moves towards the SH condition = SH Persistency % Time spent in QSH Flat top duration W n = energy of the m=1,n mode... QSH phases become more frequent and longer increasing the plasma current

IEA RFP Workshop, April Padova