stellarator presented by J. Snchez Laboratorio Nacional de Fusin, - - PowerPoint PPT Presentation

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stellarator presented by J. Snchez Laboratorio Nacional de Fusin, - - PowerPoint PPT Presentation

Transport, stability and plasma Member of control studies in the TJ-II stellarator presented by J. Snchez Laboratorio Nacional de Fusin, CIEMAT and collaborators Laboratorio Nacional de Fusin, CIEMAT, Madrid, Spain. Instituto de Plasmas e


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) ≤ m, <a> ≤

≤   ≤

) ≤ m, <a> ≤

≤   ≤

Laboratorio Nacional de Fusión, CIEMAT, Madrid, Spain. Instituto de Plasmas e Fusao Nuclear, IST, Lisbon, Portugal. Max-Planck-Institut für Plasmaphysik, Greifswald, Germany. Institute of Plasma Physics, NSC KIPT, Kharkov, Ukraine. Institute of Nuclear Fusion, RNC Kurchatov Institute, Russia. Universidad Carlos III, Madrid, Spain. Instituto Tecnológico de Costa Rica, Costa Rica. University of California-San Diego, USA A.F. Ioffe Physical Technical Institute, St Petersburg, Russia General Physics Institute, Russian Academy of Sciences, Russia National Institute for Fusion Science, Toki, Japan Instituto Tecnológico de Costa Rica, Cartago, Costa Rica.

Transport, stability and plasma control studies in the TJ-II stellarator

presented by J. Sánchez Laboratorio Nacional de Fusión, CIEMAT and collaborators

TJ-II Heliac B(0)  1.2 T, R(0) = 1.5 m, <a>  0.22 m 0.9  (0)/2  2.2 ECRH and NBI heating

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Stellarator

Development of the concept for a steady state, disruption free, high density reactor for the power plant Current free controlled configuration: “laboratory” for basic plasma physics studies relevant to tokamaks and ITER

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TJ-II research programme supporting stellarator and ITER physics

PARTICLE, ENERGY AND IMPURITY TRANSPORT: NC effects, flux surface asymmetries in plasma potential, conf. vs charge and mass FAST PARTICLE PHYSICS: Role of ECRH on Alfven Eigenmodes MOMENTUM TRANSPORT: Dynamics of Limit Cycle Oscillations and isotope effect PLASMA STABILITY STUDIES: Magnetic well scan and plasma stability POWER EXHAUST PHYSICS: Plasma facing components based on liquid metals (Li)

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TJ-II research programme supporting stellarator and ITER physics

PARTICLE, ENERGY AND IMPURITY TRANSPORT: NC effects, flux surface asymmetries in plasma potential, conf. vs charge and mass FAST PARTICLE PHYSICS: Role of ECRH on Alfven Eigenmodes MOMENTUM TRANSPORT: Dynamics of Limit Cycle Oscillations and isotope effect PLASMA STABILITY STUDIES: Magnetic well scan and plasma stability POWER EXHAUST PHYSICS: Plasma facing components based on liquid metals (Li)

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Asymmetries and impurity transport

 Evidence of long-range correlations amplification during in the proximity of the Electron-Ion root transition [M. A. Pedrosa et al., PRL 2008]  due to a reduction in neoclassical viscosity [J.L. Velasco et al., PRL-2012]

Impurity accumulation a potential problem in stellarators

Need to find “knobs” which can affect high Z transport:

 JET (2000) : asymmetries in edge radiation  J.M. Regaña (PPCF 2013, Theory): High Z imp. transport in stellarators very sensitive to 3D asymmetries of electrostatic potential

Experimental difficulty: how to “label” exactly a whole flux surface?

D B

Long range correlations along flux surfaces

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Electrostatic potential asymmetries observed

Assuming T

e variations on flux surfaces are small, in-surface floating potential differences reflect those of

plasma potential, affected by ECRH A. Alonso et al., EPS-2014 B D DF(r=0.95) Isat TECE <ne>

ECRH turn-off

ECH: ON ECH: ON ECH: OFF ECH: OFF 1 2 3 4

1 2 3 4

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F=F0 + F1 Low density Er root transition: F1 computation. NC electron-to-ion root transition occurs with relatively minor changes in n and T profiles good to test the dependence on Er. EUTERPE simulations cast large F1 and clear dependence with Er.

asymmetric part F1 at r = 0.9 Volt

Asymmetries, 3D neoclassical calculations:

Potential variation on magnetic flux surfaces in TJ-II stellarator using particle in cell (PIC) Monte Carlo code EUTERPE

See also necoclassical results on Er and transport from code FORTEC 3D (poster OV4-5)

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Charge dependence of Impurity Confinement (ECRH Plasmas)

 The dependence of impurity confinement time has been also studied as a function of charge and mass of the impurity ions. A distinct impurity confinement of injected ions is distinguished clearly in the plasma core as revealed from soft X-ray analysis and tomographic reconstructions. [B. Zurro, IAEA FEC 2014, EX/P4-43; B. Zurro, PPCF 2014 in press]

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TJ-II research programme supporting stellarator and ITER physics

PARTICLE, ENERGY AND IMPURITY TRANSPORT: NC effects, flux surface asymmetries in plasma potential, conf. vs charge and mass FAST PARTICLE PHYSICS: Role of ECRH on Alfven Eigenmodes MOMENTUM TRANSPORT: Dynamics of Limit Cycle Oscillations and isotope effect PLASMA STABILITY STUDIES: Magnetic well scan and plasma stability POWER EXHAUST PHYSICS: Plasma facing components based on liquid metals (Li)

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L-H transition near the threshold: LCOs and role of turbulence

IAEA 2010 Estrada et al., EPL 2010, PRL 2011 Gradual transitions happen for P  Ptreshold Very useful for detailed analysis of L-H transition (LCOs) Predator-prey oscillations observed between electric field and turbulence, Er following ñ

ñ

Similar predator prey behaviour observed in DIII D and AUG Schmitz et al., PRL (2012), Conway et al., PRL (2011) In 2013, HL-2A observes in addition the opposite trend (Er preceding ñ) , which leads to a different intrepretation Cheng et al., PRL (2013)

Counter Clock- Wise

p trigger model

Clock-Wise Turbulence trigger model

Doppler Reflectometry

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L-H transition near the threshold:

Experiments in TJ-II 2013-14: measure in three radial points simultaneously Multichannel Doppler reflectometry

3-point measurement allow to measure:  Propagation of the ñ and ExB flow modulation  Measurement of the Er shear: dEr/dr (parameter actually relevant in the predator-prey model )

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L-H transition near the threshold:

Using Er as x-axis: different rotation direction Using Er shear (dEr/dr) as x-axis: single rotation direction: Turbulence leads dEr/dr See Estrada et al., IAEA 2014, EX/P4-47

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The isotope effect and multi-scale physics: a possible mechanism

Larmor radius (rs) dependence of turbulent structures i.e. size of turbulent structures increases with rs

rs↑ should have

deleterious effects on transport: The mystery of the isotope effect Change in the k-spectra of turbulence Zonal flow development by inverse energy cascades via ExB symmetry breaking Beneficial effects on transport Stronger in magnetic configurations with reduced damping of zonal flows: tokamaks vs stellarators

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Long Range Correlation and H/D isotope effect: Experiments

Experimental findings show a systematic increasing in the amplitude of zonal flows during the transition from H to D dominated plasmas in TEXTOR tokamak but NOT in the TJ-II stellarator.

LRC clearly increases with D concentration

Cxy(t=0) TEXTOR (Y. Xu, C. Hidalgo et al., PRL-2013) TJ-II (B. Liu et al., EPS-2014, submitted PRL)

LRC slightly decreases with D concentration

Cxy(t=0) ECRH low density plasmas

FURTHER WORK: investigate the role of multiscale physics in the isotope effect

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TJ-II research programme supporting stellarator and ITER physics

PARTICLE, ENERGY AND IMPURITY TRANSPORT: NC effects, flux surface asymmetries in plasma potential, conf. vs charge and mass FAST PARTICLE PHYSICS: Role of ECRH on Alfven Eigenmodes MOMENTUM TRANSPORT: Dynamics of Limit Cycle Oscillations and isotope effect PLASMA STABILITY STUDIES: Magnetic well scan and plasma stability POWER EXHAUST PHYSICS: Plasma facing components based on liquid metals (Li)

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The TJ-II programme on liquid metals addresses fundamental issues like the self-screening effect of liquid lithium driven by evaporation to protect plasma- facing components against huge heat loads

Liquid Lithium Limiter: power loads and particle sources

F L Tabarés et al. PSI 2014

Power loads to the limiters evaluated through the enhanced emission of Li atoms by evaporation. Significantly lower power loads deduced compared to those derived from the edge parameters (He beam diagnostic.)

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LLL biasing is more efficient in triggering plasma confinement improvement compared to carbon limiter No deleterious effect due to the high power load induced on it was seen (deep penetration into edge plasma) Edge voltage affected 180º toroidally away

Liquid Lithium Limiter biasing experiments

F L Tabarés et al. PSI 2014

1100 1150 1200 1250 1100 1150 1200 1250 Time (s)

Ha(v) <ne>(1012cm-3)

12 10 8 6 4 2 3 2 1

  • 1
  • 2
  • 3

Vbias Li (102V)

Vfloat probe 180º away (102V)

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TJ-II research programme supporting stellarator and ITER physics

PARTICLE, ENERGY AND IMPURITY TRANSPORT: NC effects, flux surface asymmetries in plasma potential, conf. vs charge and mass FAST PARTICLE PHYSICS: Role of ECRH on Alfven Eigenmodes MOMENTUM TRANSPORT: Dynamics of Limit Cycle Oscillations and isotope effect PLASMA STABILITY STUDIES: Magnetic well scan and plasma stability POWER EXHAUST PHYSICS: Plasma facing components based on liquid metals (Li)

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Deuterio D/H≥2

Magnetic well scan & Mercier stability

LCFS is linearly coupled to the edge shear location

2,36% 1,73 1,14 0,70 0,54 0,37 0,08 0,02 0,0

Magnetic well depth % W= 2.36% W=0.32% W= -0.69%

  • 0.2 -0.1 0 0.1 0.2 0.3

R-R0 (m)

  • 0.2 -0.1 0 0.1 0.2 0.3

R-R0 (m)

0.1

  • 0.1
  • 0.2
  • 0.3
  • 0.4
  • 0.2 -0.1 0 0.1 0.2 0.3

R-R0 (m) a

Z(m)

0.1

  • 0.1
  • 0.2
  • 0.3
  • 0.4

b

Z(m)

0.1

  • 0.1
  • 0.2
  • 0.3
  • 0.4

c

Special feature of TJ-II: well scan

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Magnetic well scan: fluctuation levels and confinement

Experimental results have shown that TJ-II stellarator stability is better than standard stability analysis

  • predictions. In particular plasma confinement is not strongly affected by magnetic well although the level of

fluctuations increases in configurations without edge magnetic well. This result suggests that stability calculations, as those presently used in the optimization criteria

  • f 3-D devices, might miss some stabilization mechanisms.

[F. Castejón et al., IAEA-2014 EX/P4-45 / A. Martin de Aguilera et al., EPS-2014]

0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00

  • 1
  • 0.5

0.5 1 1.5 2 2.5 Tau_E (ms) Magnetic Well (%) ne=2 x 1019 m-3

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Dynamical coupling between gradients and transport vs magnetic well: role of non smooth profiles

Observations suggest that fluctuations are self-regulated in such a way that the most probable density gradient minimizes the size of the radial turbulent transport events Stability calculations based on smooth profiles migth miss some stabilization mechanisms, which could be explained by self-organization mechanisms between transport and gradients [B. Van Milligen et al., ICPP 2014, Hidalgo et al, PRL 2012]

FLUX GRADIENT RELATION FOR A LOCAL DIFFUSIVE PROCESS

Transport (normalized) n - n(most probable) (normalized)

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TJ-II research programme supporting stellarator and ITER physics

PARTICLE, ENERGY AND IMPURITY TRANSPORT: NC effects, flux surface asymmetries in plasma potential, conf. vs charge and mass FAST PARTICLE PHYSICS: Role of ECRH on Alfven Eigenmodes MOMENTUM TRANSPORT: Dynamics of Limit Cycle Oscillations and isotope effect PLASMA STABILITY STUDIES: Magnetic well scan and plasma stability POWER EXHAUST PHYSICS: Plasma facing components based on liquid metals (Li)

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Fast particle control: Flexible ECRH heating and unique plasma diagnostic capabilities in TJ-II

 Heavy Ion Beam Probe (potential, density and magnetic field fluctuations and profiles):  HIBP in full operation (second HIBP in commissioning)  Two 300 kW gyrotrons 2nd harmonic X mode  Steerable system  Beam size on-axis w0 = 1 cm (strongly focused) ECH1 ECH2 nII=0

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Alfven Eigenmodes: role of NBI / ECRH

  • K. Nagaoka et al., Nucl. Fusion 53 (2013) 072004/A
  • A. Cappa et al., IAEA-2014 EX/P4-46

The mitigation effect of ECRH on NBI beam-driven Alfvén eigenmodes (AE’s) reported in TJ-II suggests an attractive avenue for a possible control of the AE’s.

1192 1194 1196 1198 1200 1202 1204 1206 t (ms)

ECRH NBI ne

0,6 0,4 0,2 380 340 300 260 380 340 300 260

1100 1120 1140 1160 1180 1200 1220 #33239 Mirnov coil measurements

400 300 200

f (kHz)

1 0.5

dB(a.u.)

ECH1 250 kW, 0.42 ECH2 250 kW, 0.34

1100 1120 1140 1160 1180 1200 1220 Time (ms)

f (kHz) f (kHz)

dBpol df

ne (1019m-3)

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CONCLUSIONS

PARTICLE, ENERGY, IMPURITY TRANSPORT: Direct experimental evidence of potential flux surface asymmetries. Impurity confinement depends on mass/charge. FAST PARTICLE PHYSICS: Upon moderate off-axis ECH power application, the continuous character of the AEs changes significantly and starts displaying frequency chirping modifying the mode amplitude. This result shows that ECH can be a tool for AE control. MOMENTUM TRANSPORT: The temporal ordering of the limit cycle oscillations at the L-I-H transition linked to the radial propagation direction show leading role of turbulence. Evidence of the importance of multi-scale physics on isotope effect PLASMA STABILITY STUDIES: Stability calculations based on smooth profiles migth miss some stabilization mechanisms, which could be explained by self-organization mechanisms between transport and gradients POWER EXHAUST PHYSICS: Self-screening effect of liquid lithium driven by evaporation to protect plasma-facing components against huge heat loads. LLL biasing is more efficient in plasma confinement improvement compared to carbon limiter.

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Back-up

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Measurements and modelling of impurity flows

Flow measurements (C6+) showed an incompressible parallel flow pattern in ECRH and low-density NBI conditions (Fig. top). At higher densities systematic flow deviations are

  • bserved (Figs bottom).

Modelling resulted in density variations of 20-30 % for these higher density NBI plasmas and return parallel flows of the correct size (~ 5 km/s). However, flow correction was predicted to be of

  • pposite sign to that observed in experiments.
  • J. Arévalo , J., et al., Nucl. Fusion 53 (2013) 023003

/ Nuclear Fusion 54 (2014) 013008.

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Confinement time: Magnetic well and volume

Scaling laws predict a linear dependence of confinement time with volume. tE a a2 a Volume To distinguish the effects

  • f magnetic well and

volume, we estimate tE /

  • Vol. The same behaviour

as before.

0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00

  • 1
  • 0.5

0.5 1 1.5 2 2.5

Tau_E/Vol (ms/m-3) Well (%)