Perspectives of tearing modes control in RFX-mod Paolo Zanca Consorzio RFX, Associazione Euratom-ENEA sulla Fusione, Padova, Italy.

Slides:



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

Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Self-consistent mean field forces in two-fluid models of turbulent plasmas C. C. Hegna University of Wisconsin Madison, WI CMSO Meeting Madison, WI August.
Ideas for overseas contributions to CMSO Piero Martin Consorzio RFX Associazione Euratom-ENEA sulla fusione And Physics Dept., Univ. of Padova, Italy CMSO.
EXTENDED MHD SIMULATIONS: VISION AND STATUS D. D. Schnack and the NIMROD and M3D Teams Center for Extended Magnetohydrodynamic Modeling PSACI/SciDAC.
New schemes for MHD stability control in RFX-mod using the real-time MARTe framework Chiara Piron 3 rd PhD Event in Fusion Science and Engineering York,
November 3-5, 2003Feedback Workshop, Austin NORMAL MODE APPROACH TO MODELING OF FEEDBACK STABILIZATION OF THE RESISTIVE WALL MODE By M.S. Chu(GA), M.S.
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.
Momentum Transport During Reconnection Events in the MST Reversed Field Pinch Alexey Kuritsyn In collaboration with A.F. Almagri, D.L. Brower, W.X. Ding,
ICC2004 Madison, Wisconsin The Multi-Pinch Experiment Outline PROTO-SPHERA purpose & aims Theoretical basis & analysis Multi-Pinch: a step towards PROTO-SPHERA.
YQ Liu, Peking University, Feb 16-20, 2009 Active Control of RWM Yueqiang Liu UKAEA Culham Science Centre Abingdon, Oxon OX14 3DB, UK.
European Ph.D. course. - Garching )p.martin Piero Martin Consorzio RFX- Associazione Euratom-ENEA sulla fusione, Padova, Italy Department of Physics,
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,
Effect of sheared flows on neoclassical tearing modes A.Sen 1, D. Chandra 1, P. K. Kaw 1 M.P. Bora 2, S. Kruger 3, J. Ramos 4 1 Institute for Plasma Research,
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.
L. Zanotto, 13th RFP Workshop, Stockholm10/10/2008 Similarity experiments on RFX-mod and MST standard discharges: magnetics T. Bolzonella, P. Franz, D.
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.
Outline (HIBP) diagnostics in the MST-RFP Relationship of equilibrium potential measurements with plasma parameters Simulation with a finite-sized beam.
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.
EXPERIMENTS OF ACTIVE QSH CONTROL IN EXTRAP-T2R L. Frassinetti, P.R. Brunsell, E.K.J Olofsson and J.R. Drake.
RFA Experiments on the T2R RFP Open loop control experiments J.R. Drake 1), D. Gregoratto 2), T. Bolzonella 2), P.R. Brunsell 1), D. Yadikin 1), R. Paccagnella.
RFX-mod Workshop – Padova, January Experimental QSH confinement and transport Fulvio Auriemma on behalf of RFX-mod team Consorzio RFX, Euratom-ENEA.
23 rd SOFT September 20041/31 Control of non-axisymmetric magnetic fields for plasma enhanced performances: the RFX contribution P. Sonato, R.Piovan,
RFX-mod 2009 programme Workshop, January 20-22, 2009 Report on experimental proposals submitted to TF1 ‘RFP performance: high current operation and advanced.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
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.
R. Piovan “RFX-mod: what does...”RFX 2009 Programme Workshop Padova, Jan RFX – mod: what does the present device allow to do? R. Piovan.
The Swedish Fusion Association EURATOM – VR April 26-28, 2010EXTRAP T2R active control 1 Overview of active MHD control development on EXTRAP T2R and Output.
12/03/2013, Praga 1 Plasma MHD Activity Observations via Magnetics Diagnostics: Magnetic island Analysis Magnetic island Analysis Frederik Ostyn (UGent)
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
BGU WISAP Spectral and Algebraic Instabilities in Thin Keplerian Disks: I – Linear Theory Edward Liverts Michael Mond Yuri Shtemler.
Resonant magnetic perturbation effect on the tearing mode dynamics in EXTRAP T2R: experimental results and modeling L. Frassinetti, K.E.J. Olofsson, P.R.
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.
Modelling control P. Piovesan, A. Soppelsa in collaboration with L. Grando, G. Marchiori, L. Marrelli, L. Piron, D. Terranova, P. Zanca Consorzio RFX,
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
Tearing modes control in RFX-mod: status and perspectives P.Zanca, R.Cavazzana, L.Piron, A.Soppelsa Consorzio RFX, Associazione Euratom-ENEA sulla Fusione,
Workshop on MHD Control 2008 – O.Katsuro-Hopkins Computational analysis of advanced control methods applied to RWM control in tokamaks Oksana N. Katsuro-Hopkins.
A.Soppelsa – 7 February 2011 – RFX-mod programme workshop Session on the active control of MHD Instabilities Hot points A. Soppelsa, A. Barbalace, B. B.
Contribution of KIT to LHD Topics from collaboration research on MHD phenomena in LHD S. Masamune, K.Y. Watanabe 1), S. Sakakibara 1), Y. Takemura, KIT.
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*
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
L. Zanotto – 10 February 2011 – RFX-mod programme workshop TF2: Active control of RFP and tokamak plasmas Report on experimental proposals L. Zanotto,
RFX-mod Programme Workshop, 20-22/01/09, Padova - T. Bolzonella1 Tommaso Bolzonella on behalf of RFX-mod team Consorzio RFX- Associazione Euratom-ENEA.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
TITLE Stuart R.Hudson, D.A.Monticello, A.H.Reiman, D.J.Strickler, S.P.Hirshman, L-P. Ku, E.Lazarus, A.Brooks, M.C.Zarnstorff, A.H.Boozer, G-Y. Fu and G.H.Neilson.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
QAS Design of the DEMO Reactor
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,
Demonstration of tearing mode braking and locking due to eddy currents in a toroidal magnetic fusion device B.E. Chapman (University of Wisconsin, USA)
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,
October 2008, MPI fϋr Plasmaphysik, Garching 1 Performance limiting MHD phenomena in fusion devices: physics and active control M. Baruzzo Consorzio RFX,
Neoclassical Effects in the Theory of Magnetic Islands: Neoclassical Tearing Modes and more A. Smolyakov* University of Saskatchewan, Saskatoon, Canada,
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.
NSTX SAS – GMS Mtg. 12/1/04 S. A. Sabbagh and J. E. Menard NSTX RWM Active Feedback System Implementation Plan Discussion NSTX Global Mode Stabilization.
Current Drive Experiments with Oscillating Toroidal Flux in HT-7 Superconducting Tokamak J.S.Mao, P. Phillips 1, J.R.Luo, J.Y.Zhao, Q.L.Wu, Z.W.Wu, J.G.Li,
Design of a feedback control system for KTX Hong Li, on behalf of KTX team The 17th International RFP Workshop, October , 2015, Hefei 1.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Joint Meeting of the 3rd IAEA Technical Meeting on Spherical Tori and the 11th International Workshop on Spherical Torus St. Petersburg, 3 to 6 October.
Effects of external non-axisymmetric perturbations on plasma rotation L. Frassinetti, P.R. Brunsell, J.R. Drake, M.W.M. Khan, K.E.J. Olofsson Alfvén Laboratory,
Huishan Cai, Jintao Cao, Ding Li
Spectral and Algebraic Instabilities in Thin Keplerian Disks: I – Linear Theory Edward Liverts Michael Mond Yuri Shtemler.
15TH WORKSHOP ON MHD STABILITY CONTROL
UPDATE ON  LIMITS FOR ARIES-CS
Stabilization of m/n=1/1 fishbone by ECRH
20th IAEA Fusion Energy Conference,
Presentation transcript:

Perspectives of tearing modes control in RFX-mod Paolo Zanca Consorzio RFX, Associazione Euratom-ENEA sulla Fusione, Padova, Italy

RFX-mod contributions to TMs control (I) Demonstrated the possibility of the feedback control onto TMs Clean-Mode-Control (CMC) based on the de-aliasing of the measurements from the coils produced sidebands

RFX-mod contributions to TMs control (I) Demonstrated the possibility of the feedback control onto TMs Clean-Mode-Control (CMC) based on the de-aliasing of the measurements from the coils produced sidebands Not obvious results: phase-flip instability?

RFX-mod contributions to TMs control (I) Demonstrated the possibility of the feedback control onto TMs Clean-Mode-Control (CMC) based on the de-aliasing of the measurements from the coils produced sidebands Not obvious results: phase-flip instability? No-sign of phase-flip instability; equilibrium condition can be established where CMC induces quasi-uniform rotations of TMs

Wall-unlocking of TMs with CMC In general, the feedback cannot suppress the non-linear tearing modes requested by the dynamo. The feedback keeps at low amplitude the TMs edge radial field Improvement of the magnetic structure: sawtooth of the m=1 n=-7 which produces transient QSH configurations RFX-mod contributions to TMs control (II)

Increase the QSH duration → recipes under investigation Which are the possibilities to reduce further the TMs edge radial field? → Model required CMC optimizations

RFXlocking Semi-analitical approach in cylindrical geometry Newcomb’s equation for global TMs profiles Resonant surface amplitudes imposed from experiments estimates Viscous and electromagnetic torques for phase evolution Radial field diffusion across the shell(s) Feedback equations for the coils current It describes fairly well the RFX-mod phenomenology →L.Piron talk

General analysis of the TM control

plasma SensorsCoilsVessel Single-shell external coils

Normalized edge radial field The feedaback action keeps low the normalized edge radial field At best b ^ sens can be made close but not smaller than the ideal-shell limit

plasma SensorsCoilsVessel Feedback limit

plasma SensorsCoilsVessel Feedback limit

plasma Sensors b r =0 everywhere: impossible CoilsVessel Feedback limit

Role of the Vessel The stabilizing effect of the vessel is crucial for having low b ^ sens and moderate power request to the coils The shorter τ w the faster must be the control system (f c =1/Δt) to avoid feedback (high-gain) induced instabilities Optimum range: τ w >10ms better τ w  100ms

plasma Sensors Coils Vessel Single-shell Internal coils

plasma Sensors Coils Vessel Single-shell Internal coils

Continuous-time feedback → solution ω  ω 0 with b r (r sens )  0 for large gains Discrete-time feedback : including the latency Δt the high- gain instability may occur The good control region is not accessible for realistic TM amplitudes. For stable gains b ^ sens is determined by the ideal-shell limit, which is large due to the loose-fitting vessel required by the coils dimension

RFP design for good TM control (a personal view)

Premise The passive stabilization provided by a thick shell does not solve the wall-locking problem In the thick-shell regime wall-locking threshold ~σ 1/4 Feedback is mandatory to keep TMs rotating

Design in outline In-vessel coils not interesting Single structure (vessel=stabilizing shell) with the coils outside Close-fitting vessel to reduce the ideal-shell limit τ w  10ms-100ms with Δt  10μs-100μs

RFX-mod perspectives (a personal view)

RFX-mod layout 3ms vacuum-vessel, 100ms copper shell, ~25ms mechanical structures supporting the coils The control limit is mainly provided by the 100ms copper shell

RFX-mod status Gain optimization guided by RFXlocking simulations for the RFX-mod case m=1 TMs

Optimizations Get closer to the ideal-shell limit (minor optimization) Reduce the ideal-shell limit by hardware modifications (major optimization)

Minor optimizations Increase the coils amplifiers bandwidth: maximum current and rensponse time Acquisition of the derivative signal db r /dt in order to have a better implementation of the derivative control (to compensate the delay of the coils amplifiers) Compensation of the toroidal effects by static decoupler between coils and sensors only partially exploited Compensation of the shell non-homogeneities requires dynamic decoupler (work in progress)

Major optimization Approach the shell to the plasma edge possibly simplifying the boundary (removing the present vacuum vessel which is 3cm thick) Moving the τ w =100ms shell from b=0.5125m to b=0.475m (a=0.459) a factor 3 reduction of the edge radial field is predicted by RFXlocking

Conclusions CMC keeps TMs into rotation Edge radial field: ideal-shell limit found both with the in- vessel and out-vessel coils → b r (a)=0 cannot be realized The vessel=shell must be placed close the plasma → coils outside the vessel. Is a close-fitting vessel implementable in a reactor? The feedback helps the vessel to behave close to an ideal shell → τ w cannot be too short

spare

Edge radial field control by feedback

RFXlocking.vs. experiment

Normalized edge radial field: weak b rs dependence

b r (r m,n ) vs b r (a) experimental

Locking threshold The present analysis valid for  w <<r w cannot be extrapolated to very long  w

Edge radial field.vs. current time constant

a = 0.459m r w i = 0.475m c = m Single mode simulations: external coils

Single-mode analysis: feedback performances dependence on  w

Multi-mode analysis: power dependence on  w

Edge radial field:  w dependence Data averaged on 0.1s simulation m=1

Normalized edge radial field: r wi dependence m=1

Normalized edge radial field: no r f dependence m=1

Out-vessel coils: signals 4x48 both for coils (c = m) and sensors (r wi = 0.475m )

Single-shell: discrete feedback Δt = latency of the system

External coils: discrete feedback τ w =100ms

External coils: discrete feedback τ w =10ms

External coils: discrete feedback τ w =1ms

The in-vessel coils

Single mode simulations: frequency τ w = 1ms  100ms

Single mode simulations: I c, V c

Single mode simulations: edge b r

Multi-mode simulations: frequencies Averages over the second half of the simulation

Multi-mode simulations: plasma surface distortion

Multi-mode simulations: no phase-locking Ideal shell feedback

Multi-mode simulations: no phase-locking Incompatible with

Internal coils: discrete feedback stable solutions

The MHD model: Ψ wi, Ψ we Boundary conditions from Newcomb’s solution

The MHD model: Ψs From experiment No-slip condition

The MHD model: Ω θ, Ω Φ

The MHD model: δT EM

The MHD model: Ψ c Further variable: I c m,n

The MHD model: I c Further variable: I REF m,n RL equation for the plasma-coils coupled system

The MHD model: I REF Acquired by the feedback

Why a pure derivative control? When |   c m,n |>>1, from the RL equation one gets