Internal Transport Barrier Triggering by Rational Magnetic Flux Surfaces in Tokamaks

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

MHD Internal Transport Barrier Triggering in Low Positive Magnetic Shear Scenarios in JET

EX8/3 22nd IAEA Fusion Energy Conference Geneva

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET

A Dimensionless Criterion for Characterising Internal Transport Barriers in JET

Turbulent Transport Analysis of JET H-mode and Hybrid Plasmas using QuaLiKiz, TGLF and GLF23

Comparison of theory-based and semi-empirical transport modelling in JET plasmas with ITBs

Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography

INTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, October 2008

Comparative Transport Analysis of JET and JT-60U Discharges

Progress in Transport Modelling of Internal Transport Barrier Plasmas in JET

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

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus)

Experimental Evidence of Inward Momentum Pinch on JET and Comparison with Theory

Core Transport Properties in JT-60U and JET Identity Plasmas

ITR/P1-19 Tokamak Experiments to Study the Parametric Dependences of Momentum Transport

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Divertor Power Handling Assessment for Baseline Scenario Operation in JET in Preparation for the ILW

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

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

Triggering Mechanisms for Transport Barriers

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

Electron Transport and Improved Confinement on Tore Supra

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

Modelling of Carbon Erosion and Deposition in the Divertor of JET

Onset of Tearing Modes in JET Advanced Scenarios

Upgrade of the Present JET Shape and Vertical Stability Controller

Progressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DT Fusion Power Production in ELM-free H-modes in JET

Dimensionless Identity Experiments in JT-60U and JET

Understanding Confinement in Advanced Inductive Scenario Plasmas Dependence on Gyroradius and Rotation

Key Quantities for ITB Formation and Sustainment

STUDY OF ADVANCED TOKAMAK PERFORMANCE USING THE INTERNATIONAL TOKAMAK PHYSICS ACTIVITY DATABASE

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

Bursty Transport in Tokamaks with Internal Transport Barriers

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

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

Characterization of ion heat conduction in JET and ASDEX Upgrade plasmas with and without internal transport barriers

Understanding physics issues of relevance to ITER

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

Influence of Impurity Seeding on ELM Behaviour and Edge Pedestal in ELMy H-Mode Discharges

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

Observation of modes at frequencies above the Alfvén frequency in JET

Spectroscopic Determination of the Internal Amplitude of Frequency Sweeping TAE

Confinement and edge studies towards low ρ* and ν* at JET

Micro-stability and Transport Modelling of Internal Transport Barriers on JET.

C-Mod Transport Program

ENERGETIC PARTICLES AND BURNING PLASMA PHYSICS

TURBULENT TRANSPORT THEORY

MHD stability analysis of diagnostic optimized configuration shots in JET

Improved Confinement in JET High b Plasmas with an ITER-Like Wall

High-m Multiple Tearing Modes in Tokamaks: MHD Turbulence Generation, Interaction with the Internal Kink and Sheared Flows

Experimental Study of the Stability of Alfvén Eigenmodes on JET

Time-Frequency Analysis of Non-Stationary Signals in Fusion Plasmas Using the Choi-Williams Distribution

Global particle-in-cell simulations of Alfvénic modes

Alfvén cascades in JET discharges with NBI-heating

MHD Induced Fast-Ion Losses in ASDEX Upgrade

Experimental studies of ITER demonstration discharges

MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling

Characteristics of the H-mode H and Extrapolation to ITER

Development and Validation of a Predictive Model for the Pedestal Height (EPED1)

Introduction to Fusion Physics

Dimensionless Identity Experiments in JT-60U and JET

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

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

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

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

L Aquila, Maggio 2002

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

Combined LH and ECH Experiments in the FTU Tokamak

Spectroscopic determination of the internal amplitude of frequency sweeping TAE

NumKin, Strasbourg, October 17 th, 2016

Edge Momentum Transport by Neutrals

Progress towards steady-state operation and real-time control of internal transport barriers in JET

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

Power Exhaust on JET: An Overview of Dedicated Experiments

Overview of results from MAST Presented by: Glenn Counsell, for the MAST team

Particle transport results from collisionality scans and perturbative experiments on DIII-D

Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET

Flux-driven multi-channel simulations with the quasilinear gyrokinetic tokamak transport model QuaLiKiz

On the physics of shear flows in 3D geometry

Multimachine Extrapolation of Neoclassical Tearing Mode Physics to ITER

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

EX/4-2: Active Control of Type-I Edge Localized Modes with n = 1 and n = 2 fields on JET

Plasma turbulence measured by fast sweep reflectometry on TORE SUPRA

1 THC/P4-01. Shear flow suppression of turbulent transport and self-consistent profile evolution within a multi-scale gyrokinetic framework

ICRF Mode Conversion Flow Drive on Alcator C-Mod and Projections to Other Tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

W.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA

Energetic Particle Physics in Tokamak Burning Plasmas

Modification of sawtooth oscillations with ICRF waves in the JET tokamak

Magnetic Flux Surface Measurements at Wendelstein 7-X

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

q(0) pressure after crash 1.0 Single tearing on q=2 Double tearing on q=2 0.5

Effects of Alpha Particle Transport Driven by Alfvénic Instabilities on Proposed Burning Plasma Scenarios on ITER

Benchmarking of electron cyclotron heating and current drive codes on ITER scenarios within the European Integrated Tokamak Modelling framework

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

Transcription:

EFDA JET CP(0)07/09 E. Joffrin, C.D. Challis, G.D. Conway, X. Garbet, A. Gude, S. Guenther, N. C. Hawkes, T.C. Hender, D. Howell, G.T.A. Huysmans, E. Lazarro, P. Maget, M. Marachek, A.G. Peeters, S.D. Pinches and S. Sharapov Internal Transport Barrier Triggering by Rational Magnetic Flux Surfaces in Tokamaks

.

Internal Transport Barrier Triggering by Rational Magnetic Flux Surfaces in Tokamaks E. Joffrin 1, C.D. Challis, G.D. Conway 3, X. Garbet 1, A. Gude 3, S. Guenther 3, N. C. Hawkes, T.C. Hender, D. Howell, G.T.A. Huysmans 1, E. Lazarro 4, P. Maget 1, M. Marachek 3, A.G. Peeters 3, S.D. Pinches 3, S. Sharapov, and contributors to the EFDA-JET workprogramme* 1 Association Euratom-CEA, Cadarache, F-13108, France. Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxfordshire, OX14 3DB, UK. 3 Max-Planck-Institut fur Plasmaphysik, Euratom Association, 85748, Garching Germany. 4 Istituto di Fisica del Plasma del CNR, Assoc. Euratom-ENEA-CNR per la Fusione, 015 Milan Italy. * See annex of J. Pamela et al, Overview of Recent JET Results and Future Perspectives, Fusion Energy 000 (Proc. 18 th Int. Conf. Sorrento, 000), IAEA, Vienna (001). Preprint of Paper to be submitted for publication in Proceedings of the 19th IAEA Conference, (Lyon, France 14-19 October 00)

This document is intended for publication in the open literature. It is made available on the understanding that it may not be further circulated and extracts or references may not be published prior to publication of the original when applicable, or without the consent of the Publications Officer, EFDA, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK. Enquiries about Copyright and reproduction should be addressed to the Publications Officer, EFDA, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK.

ABSTRACT. The formation of Internal Transport Barriers (ITBs) has been experimentally associated with the presence of rational q-surfaces in both JET and ASDEX Upgrade. The triggering mechanisms are related to the occurrence of magneto-hydrodynamic (MHD) instabilities such as mode coupling or fishbone activity. These events could locally modify the poloidal velocity and increase transiently the shearing rate to values comparable to the linear growth rate of ITG modes. For reversed magnetic shear scenario, ITB emergence occurs preferentially when the minimum q reaches an integer value. In this case, transport effects localised in the vicinity of zero magnetic shear and close to rational q values may also contribute to the formation of ITBs.The role of rational q surfaces on ITB triggering stresses the importance of q profile control for advanced tokamak scenario and could contribute to lower substantially the access power to these scenarios in next step facilities. 1. INTRODUCTION Recently, it was identified in JET [1] and ASDEX Upgrade [] that rational q-surfaces and in particular low order q rational are playing a key role in the internal transport barrier (ITB) formation for both reversed and low positive magnetic shear. The variety of q-profile is usually obtained in the plasma current ramp-up using various combination of heating schemes. In JET, for example, low positive shear target profiles are obtained without any heating or with small level of Ion Cyclotron Resonance Heating (ICRH) power. Strong reversed magnetic shear profiles are created by preheating the plasma with Lower Hybrid Current Drive (LHCD). The combined effect of off-axis current drive and electron heating by the lower hybrid wave can result in very large value of q o. This tailoring of the target current profile has made possible the study of the ITB triggering mechanism for different value of the magnetic shear in the plasma centre. This paper first summarises the experimental evidence showing the relation between rational surfaces and ITB emergence. The role of MHD events taking place on these integer q-surfaces is presented for ASDEX-Upgrade and low positive magnetic shear in JET. In the fourth section, an explanation for the creation of ITB in reversed magnetic shear at q min = or 3 is also put forward on the basis of the recent theoretical works on rational surface rarefaction.. RELATION BETWEEN RATIONAL SURFACE AND INTERNAL TRANSPORT BARRIER FORMATION Several independent experimental studies in JET and ASDEX Upgrade have confirmed that rational surface are at the origin of the internal transport barrier for both low positive and strongly reversed shear. In ASDEX Upgrade, the emergence of ITB in reversed magnetic shear has been related to the presence of fishbone on the q = surface []. In JET, internal transport barriers have been observed in correlation with integer q surface such as q = 1, or 3 for low positive shear discharges [1]. More recent experiments have extended this analysis to reversed shear target q profile [3]. Figure 1a shows the effect of the main heating power (NBI + ICRH) on the ITB formation. As the power increases, the emergence of the ITB determined by the JET ITB criterion [4] is delayed. The 1

determination of q profiles from motional Stark effect and infrared polarimetry shows that this emergence time coincides with the time when qmin reaches (fig 1b). The fact that the ITB is triggered when qmin reaches, confirms that the access to the ITB regime is not clearly linked to the input power, but rather to an optimum q profile when the main heating is applied. The presence of the q = surface at qmin is experimentally confirmed by the detection of n = to n = 6 Alfvèn which can only occur when the condition m-n.q min (t) = 0 and is fulfilled as qmin passes q = [3]. This analysis is showing that the emergence of the ITB does not depend on the input power but on the presence of integer q-surfaces close to the low or zero shear regions. The importance of rational surface stresses the role of the q profile in the ITB formation and the need for the q profile control for advanced tokamak operation. 3. ITB TRIGGER MECHANISMS IN ASDEX-UPGRADE Recent observations [] have indicated that the formation of internal transport barriers in ASDEX -Upgrade are preceded by fishbone activity on q-surfaces such as q=, i.e. oscillation of the internal kink driven by the fast ion population. The mechanism by which this happens relies on the interaction between these fast ions with the kink distortion of the magnetic field. The time evolution of the fast ion radial current has been computed using the radial magnetic structure of the mode inferred from experimental data from the electron cyclotron emission (ECE) and magnetic diagnostics. From this radial current, the effective radial electric field is inferred and the produced sheared ExB flow deduced. A comparison of the shearing rate calculated for ASDEX Upgrade parameters indicates that fishbones with a sufficiently high repetition frequency (typically above the effective collision time scale) give shearing rate comparable with estimates of the linear growth rate of ITG modes. Fishbones are thus a suitable candidate for the triggering of internal transport barriers. 4. TRIGGER MECHANISM IN LOW POSITIVE MAGNETIC SHEAR IN JET. In JET, a recent experimental study has shown that the ITB emergence is well correlated with an external kink mode is destabilised as an integer q surface (q = 4, q = 5 or q = 6) enters the plasma in the current ramp-up [1]. Since ITBs are formed in the vicinity of internal integer q surfaces, toroidal mode coupling has been put forward as the most plausible candidate mechanism to explain the link between the edge MHD occurrence and the ITB emergence time. Simulations with the CASTOR code have confirmed that strong mode coupling can occur between the edge MHD mode and the internal q surface. The destabilisation of the MHD at q = or q = 3 by the coupling process could provide a locally enhanced sheared flow by mode braking, and act as a trigger for the ITB formation. To examine this hypothesis and evaluate the effect of mode braking on plasma flow, the model shown below make use of the linearised MHD equations including toroidal effect between two resonant layers. The resonance layers are supposed to be in the non-linear regime and the plasma response is determined by diamagnetism and transverse transport (diffusion and viscosity). These equations are solved together with the evolution equations for the plasma flow in both toroidal and

poloidal directions. The system of coupled equations between the poloidal and toroidal rotation and the growth rates (or ) of the edge and internal modes is calculated from the variational principle for a given n number (here n=1). The coupled equation for the evolution of the normalised island width W and phase φ are expressed for each resonant surface as [5]: W C R b b = '. t b + s b W b W b.cos(φ e - φ b ) and W R e e = ' t b + W b W b C.s b. cos(φ e - φ b ) and φ b t φ e t * C = k θ.v b + k θ.v θb + k ϕ.v ϕb +.W e.w b.sin(φ e - φ b ) κ b.s b * C.s = k θ.v e + k θ.v θe + k ϕ.v ϕb - b.w b.w e.sin(φ e - φ b ) κ e In these equations, the index b denotes the quantities at the barrier location and e at the edge. C is the coupling parameter and is approximated by C~a/R. R b, R e and s b, s e are respectively the resistive times and the magnetic shears at each resonant surface. Finally κ b (and κ e ) given in [6]: qr 1 κ b = 88.D.β θ...c s, s b.a k θ.a using the Gyro-Bohm approximation for the diffusion coefficient D and where c s is the sound speed. The equation of motion for the plasma in the toroidal and poloidal direction at the location of the rational surface are described by: V m.n. θ = P t θ - m.n.ν neo (V θ - k neo - V * V ) and m.n. θ t = P ϕ + m.n. 1. d r dr rµ dv θ dr V * is the diamagnetic velocity, ν neo = ν ii.q.(r/a) 3/, µ the viscosity and k neo ~ 1.17 in the collisionless regime. P θ and P ϕ are the poloidal and toroidal momentum per unit volume transferred to the plasma by the mode on the considered resonance layers. This momentum will act on the plasma over a spatial range determined by a form factor L such that L(ρ).dρ where ρ = r/a is the normalised radius. This function L depends on the model employed outside the island separatrix. In the present calculation, the behaviour of the flow shear away from the separatrix of the island is described as in reference [7] taking into accound the diamagnetic effect in the vicinity of the island. In this case, the function L is decribed by an exponential and the typical width of the region where the plasma is µ entrained by the island is extimated to be: λ = ρ s. D, where ρ s is the ion larmor radius. In steady state and without mode coupling, one can note from the above equations that the plasma at the rational surface will rotate with the diamagnetic frequency in the poloidal direction and with the neutral beam momentum in the toroidal direction. In the test case, the q = surface is chosen as the internal surface and the external surface q = 4 is artificially destabilised by an increase of its e. This choice reproduces the observed experimental situation where the external mode on the q = 4 surface is destabilised by an excess of edge current and couples with the q = surface at the ITB location. Figure 3 shows the behaviour of the poloidal and toroidal velocity using typical plasma parameters (Te = kev, BT =.6T, ne =.10 19 m -3 ). The 3

edge pertubation is simulated by an increase of De from 0 to, corresponding to an edge perturbation ~ Bq/Bq10-3. The poloidal velocity starts to oscillate with an amplitude of about 400m/s. This oscillation indicates that the two resonant surfaces are not locked to each other but are in an intermediate state where the edge mode starts to brake the growing q = island. The change in toroidal rotation is relatively modest and the island at the q = surface increases to a size of less than cm. This is making difficult the detection of this island by magnetic measurements on the wall of the vacuum vessel. However, the effective change of poloidal rotation (~00m/s) imposed by the q = island will strongly modify the shear flow outside the island separatrix. Using the cylindrical definition of Hahm and Burrell [8], the shear rate is defined for the case of low magnetic shear and sharp electric field gradients: d dr E r d V 5 10 B o dr 4 s -1 θ γ E and γ lin k θ.γ s = V th a.r =. 105 s -1 showing that mode braking is capable of triggering an ITB by inducing strong local shearing rate exceeding the linear growth rate of ITG turbulence for k θ.ρs of the order of 0.1. 5. TRIGGER MECHANISM IN REVERSED MAGNETIC SHEAR IN JET. In reversed shear q profile the emergence of ITBs has also been confirmed to correlated with s = 0 reaching a rational magnetic q-surface such as or 3 as explained in section 1. Figure 4a shows the evolution of the temperature gradient as the zero shear point reaches the rational surface q =. From this point, two internal transport barriers develop at two different radial locations: one in the negative shear and the other in the positive shear region. This behaviour looks quite systematic and has been described in more details in reference [3]. It cannot be explained only by the velocity shear argument. This would be indeed coincidental to see the strong shear flow propagating in two different directions radially. In addition, no MHD activity has been in general observed at the time of the ITB formation in contrast to the low positive shear case. On the other hand, the argument of the rarefaction of flux surfaces already put forward by previous authors [9, 10] could provide an explanation for this behaviour. In the vicinity of low order rational surface, sharp barrier could develop at the location of zero magnetic shear. The rarefaction of resonant surfaces around low order rational q can create gaps which are not balanced by an increase of the turbulence radial correlation length. The width of the gap scales as the square root of the Larmor radius and depend on the curvature of the q profile as: d gap =.q min.ρ i n.r min.q" min When this gap width exceeds the turbulence correlation length L c (scaling like ρ i for gyro-bohm scaling), simulation are suggesting that an internal transport barrier can be formed [9]. It should be 1/ noted that the q profile (i.e. q ) is the dominant factor in d gap since ρ i scales as T e /Bo which is itself roughly constant with the plasma radius r. 1 4

The evolution of the gaps between resonant surfaces has been computed for pulse 51579. The experimental q profile shape is scanned across the q= surface and the gaps calculated for toroidal and poloidal number up to 80 (fig 4b), i.e. k θ ρ s ~0.1. When the q = surface is reached a large gap opens and then two gaps on each side of the q = surfaces propagating on each side of q min. Shortly after, it appears that high n and m resonant surfaces are developing in between these two gaps, dividing them and making possible the formation of two internal transport barrier at two different radial location as observed by the experiment. This indicates that the evolution of rational surfaces around a low integer q-surface could be at the origin of the formation of the two observed ITBs. CONCLUSIONS The analysis of ITB triggering mechanism in JET and ASDEX-Upgrade has demonstrated that the physics properties (MHD and transport) of resonant surfaces are essential for the understanding of ITB formation. Ultimately the knowledge and the control of the triggering conditions to form an ITB will assist in minimising the required input power to access ITB regimes in advanced tokamak plasmas for larger size devices. REFERENCES [1]. E. Joffrin et al. Nuc Fus 4 (00) 35 []. S. Pinches et al. 8 th EPS Conference on Control. Fusion and Plasma Physics 5A P1.008 [3]. E. Joffrin et al. Plasma Physics and Controlled Fusion 44 (00) 1739 [4]. G. Tresset et al. Nuc Fus 4 (00) 50 [5]. D. Edery and A. Samain, Plasma Physics and Controlled Fusion 3 (1990) 93 [6]. A. Samain, Plasma Physics and Controlled Fusion 6 (1984) 731 [7]. J. W. Connor et al., Phys. Plasma 8 (001) 835 [8]. T. S. Hahm and K.H. Burrell, Phys. Plasma 1648 [9]. X. Garbet et al, Phys. Plasma 8 (001) 793 [10]. F. Romanelli and F. Zonca, Phys. Fluids B 5 4081 5

16 a) Pulse No: 51573 37 Pulse No: 1391 Input power (MW) 1 10 4.5 b) t heat = 4.3s Pulse No: 51586 Pulse No: 51579 t heat = 4.0s Frequency (khz) 30.9 5.8 1.5 T i (kev) 8 4 t = 1.48s t = 1.68s q min.0 1.5 1.0 0.8 1.0 1. 1.4 1.6 1.8.0 Time from t heat (s) JG0.430-6c 18.0 4 0 0.4 0.8 Radius, ρ 15.0 1.50 1.54 1.58 1.6 1.66 Time (s) 1.70 JG03.84-1c Figure 1 (a) & (b): Emergence time of the ITB in strong reversed shear. The ITB triggering does not appear to depend on the input power level but is correlated with qmin reaching the q = surface. (t heat is the time when the main heating is applied) Figure : Fishbone activity (arrow)at the ITB emergence in ASDEX-Upgrade. e Wb (cm) Vφ (km/s) Vθ (km/s).0 1.9 1.8 100.5 100.0 0.0 0.01 0 1 0 0 0. 0.4 0.6 0.8 1.0 Time (s) JG0.430-10c Figure 3; Simulation of the poloidal and toroidal flow at the q = surface when an edge perturbation grows at the q = 4 surface at the edge. 6

Pulse No: 51594 Degree of confidence above ρ*t = 0.01(%) Pulse No: 51594 d gap (cm) 0.7 90 0.7 q = 0.1 Normalised radius 0.6 0.5 0.4 80 70 Normalised radius 0.6 0.5 0.4 0.08 0.3 60 0.3 0.04 0. 6.0 6.1 6. 6.3 6.4 6.5 Time (s) JG0.430-1c 50 0. -0.1 0 0.1 0. 0.3 0.4 Time (s) JG0.430-11c 0 Figure 4 (a): ITB criterion calculated for Pulse No: 51591. When the q min reaches q = two ITB are created on each side of q min. Figure 4(a): Simulation of the gaps between rational surfaces up to n = m = 80, as a reversed q profile is scanned across the q = surface. 7