Ripple losses during ICRF heating in Tore Supra

Basiuk, V.; Eriksson, L.‐G.; Bergeaud, V.; Chantant, M.; Martín, G.; Nguyen, Frédéric; Reichle, R.; Vallet, J.C.; Delpeche, L.; Surle, F.

doi:10.1088/0029-5515/44/1/020

Cited by 42 publications

(48 citation statements)

References 21 publications

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“…The major points that were understood on ripple losses at the time of the publication of the ITER Physics Basis were: (1) ripple losses are numerically predictable as indicated by experiments in JET [53], JT-60U [54] and TFTR [10]; (2) ripple losses of α-particles in ITER are anticipated to be negligible in discharges with monotonic, positive magnetic shear [3]; (3) on the other hand, the losses can be a concern in advanced operation scenarios based on reversed shear. Since the writing of the ITER Physics Basis, publications on ripple loss experiments have appeared for TFTR [6,10,55,56], JFT-2M [57][58][59] and Tore Supra [60,61].…”

Section: Ripple-induced Lossesmentioning

confidence: 99%

Chapter 5: Physics of energetic ions

et al. 2007

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This chapter reviews the progress accomplished since the redaction of the first ITER Physics Basis Nucl. Fusion 39 2137 in the field of energetic ion physics and its possible impact on burning plasma regimes. New schemes to create energetic ions simulating the fusion-produced alphas are introduced, accessing experimental conditions of direct relevance for burning plasmas, in terms of the Alfvénic Mach number and of the normalised pressure gradient of the energetic ions, though orbit characteristics and size cannot always match those of ITER. Based on the experimental and theoretical knowledge of the effects of the toroidal magnetic field ripple on direct fast ion losses, ferritic inserts in ITER are expected to provide a significant reduction of ripple alpha losses in reversed shear configurations. The nonlinear fast ion interaction with kink and tearing modes is qualitatively understood, but quantitative predictions are missing, particularly for the stabilisation of sawteeth by fast particles that can trigger neoclassical tearing modes. A large database on the linear stability properties of the modes interacting with energetic ions, such as the Alfvén eigenmode has been constructed. Comparisons between theoretical predictions and experimental measurements of mode structures and drive/damping rates approach a satisfactory degree of consistency, though systematic measurements and theory comparisons of damping and drive of intermediate and high mode numbers, the most relevant for ITER, still need to be performed. The nonlinear behaviour of Alfvén eigenmodes close to marginal stability is well characterized theoretically and experimentally, which gives the opportunity to extract some information on the particle phase space distribution from the measured instability spectral features. Much less data exists for strongly unstable scenarios, characterised by nonlinear dynamical processes leading to energetic ion redistribution and losses, and identified in nonlinear numerical simulations of Alfvén eigenmodes and energetic particle modes. Comparisons with theoretical and numerical analyses are needed to assess the potential implications of these regimes on burning plasma scenarios, including in the presence of a large number of modes simultaneously driven unstable by the fast ions.

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Section: Ripple-induced Lossesmentioning

confidence: 99%

Chapter 5: Physics of energetic ions

et al. 2007

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“…$0.011 * E ICRH . The most likely mechanism is the stochastic diffusion of fast ions orbits due to the strong magnetic ripple [4,5], resulting in loss of non-thermal ions ($500 keV) on the low field side, below or at the mid-plane, as also observed in JT-60 [6]. Most of the long discharges with LHCD + ICRH carried out in Tore Supra in 2004-2005 were at low plasma current (I P = 0.6 MA) and at low electron density (n e $ 2.5 · 10 19 m À3 ), in order to have a large fraction of non-inductive current with LHCD.…”

Section: Calorimetric Measurementsmentioning

confidence: 99%

Thermal and non-thermal particle interaction with the LHCD launchers in Tore Supra

Goniche

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Basiuk

et al. 2007

Journal of Nuclear Materials

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“…The nominal operating frequency is adjusted in order for the wave energy to be deposited in the central region to prevent W accumulation [36,37]. However, due to the finite magnetic ripple level expected in WEST, the fast ions produced by ICRH can be deconfined [38]. As an illustration, figure 9 shows the good confinement region size which is affected by the value of the plasma current.…”

Section: Ion Cyclotron Resonance Heatingmentioning

confidence: 99%

WEST Physics Basis

et al. 2015

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56 075020) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L-H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas.

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Ripple losses during ICRF heating in Tore Supra

Cited by 42 publications

References 21 publications

Chapter 5: Physics of energetic ions

Chapter 5: Physics of energetic ions

Thermal and non-thermal particle interaction with the LHCD launchers in Tore Supra

WEST Physics Basis

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