Journal ArticleDOI
Chapter 3: MHD stability, operational limits and disruptions
T. C. Hender,J.C. Wesley,J.M. Bialek,Anders Bondeson,Allen H. Boozer,R.J. Buttery,Am Garofalo,Timothy Goodman,Robert Granetz,Y. Gribov,O. Gruber,Mikhail Gryaznevich,G. Giruzzi,Sibylle Günter,Nobuhiko Hayashi,Per Helander,Chris Hegna,D. F. Howell,D.A. Humphreys,G. T. A. Huysmans,A.W. Hyatt,Akihiko Isayama,Stephen Jardin,Yasunori Kawano,A. Kellman,C.E. Kessel,H. R. Koslowski,R. J. La Haye,E. Lazzaro,Yueqiang Liu,V.E. Lukash,J. Manickam,S. Medvedev,V. Mertens,S. V. Mirnov,Y. Nakamura,G.A. Navratil,M. Okabayashi,Takahisa Ozeki,Roberto Paccagnella,G. Pautasso,F. Porcelli,V. D. Pustovitov,V. Riccardo,M. Sato,Olivier Sauter,M.J. Schaffer,Michiya Shimada,Piergiorgio Sonato,E. J. Strait,M. Sugihara,Manabu Takechi,A. D. Turnbull,E. Westerhof,D.G. Whyte,R. Yoshino,H. Zohm +56 more
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A review of recent advances in the area of MHD stability and disruptions, since the publication of the 1999 ITER Physics Basis document (1999 Nucl. Fusion 39 2137-2664), is reviewed in this paper.Abstract:
Progress in the area of MHD stability and disruptions, since the publication of the 1999 ITER Physics Basis document (1999 Nucl. Fusion 39 2137-2664), is reviewed. Recent theoretical and experimental research has made important advances in both understanding and control of MHD stability in tokamak plasmas. Sawteeth are anticipated in the ITER baseline ELMy H-mode scenario, but the tools exist to avoid or control them through localized current drive or fast ion generation. Active control of other MHD instabilities will most likely be also required in ITER. Extrapolation from existing experiments indicates that stabilization of neoclassical tearing modes by highly localized feedback-controlled current drive should be possible in ITER. Resistive wall modes are a key issue for advanced scenarios, but again, existing experiments indicate that these modes can be stabilized by a combination of plasma rotation and direct feedback control with non-axisymmetric coils. Reduction of error fields is a requirement for avoiding non-rotating magnetic island formation and for maintaining plasma rotation to help stabilize resistive wall modes. Recent experiments have shown the feasibility of reducing error fields to an acceptable level by means of non-axisymmetric coils, possibly controlled by feedback. The MHD stability limits associated with advanced scenarios are becoming well understood theoretically, and can be extended by tailoring of the pressure and current density profiles as well as by other techniques mentioned here. There have been significant advances also in the control of disruptions, most notably by injection of massive quantities of gas, leading to reduced halo current fractions and a larger fraction of the total thermal and magnetic energy dissipated by radiation. These advances in disruption control are supported by the development of means to predict impending disruption, most notably using neural networks. In addition to these advances in means to control or ameliorate the consequences of MHD instabilities, there has been significant progress in improving physics understanding and modelling. This progress has been in areas including the mechanisms governing NTM growth and seeding, in understanding the damping controlling RWM stability and in modelling RWM feedback schemes. For disruptions there has been continued progress on the instability mechanisms that underlie various classes of disruption, on the detailed modelling of halo currents and forces and in refining predictions of quench rates and disruption power loads. Overall the studies reviewed in this chapter demonstrate that MHD instabilities can be controlled, avoided or ameliorated to the extent that they should not compromise ITER operation, though they will necessarily impose a range of constraints.read more
Citations
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Electromagnetic VDE and Disruption Analysis in the SMART Tokamak
Anna Sara Zanolla Mancini,Steven J. Doyle,J. Segado-Fernandez,J. Ayllon-Guerola,D. J. Cruz-Zabala,J. Garcia-Dominguez,M. Garcia-Munoz,E. Viezzer,P.F. Buxton,Kyoung-Jae Chung,Mikhail Gryaznevich,Y.S. Hwang,J. García López +12 more
TL;DR: In this paper , the structural analysis of the SMALL aspect ratio tokamak (SMART) is performed for the design and verification of structural integrity during normal and off-normal operations.
Proceedings ArticleDOI
Tokamaks images advanced processing for diagnostics
TL;DR: In this paper , a strategy based on the reconstruction of the runaway electrons beam allows to infer plasma characteristic parameters which allows for an advanced real-time monitoring of the nuclear fusion experiment.
Journal ArticleDOI
Simulation of hard X-ray time evolution in plasma tokamak by using the NARX-GA hybrid neural network
Journal ArticleDOI
Torque to counter-current direction driving low frequency tearing modes in JT-60U
T. Bando,M. Honda,S. Inoue,Minoru Yoshida,Go Matsunaga,Akihiko Isayama,Manabu Takechi,Kouji Shinohara,S. Sumida +8 more
TL;DR: In this paper, the authors investigated the effect of the torque balance between the NTV torque and the torque induced by the eddy current on the resistive wall in a JT-60U tokamak.
Journal ArticleDOI
Electromagnetic VDE and Disruption Analysis in the SMART Tokamak
TL;DR: In this paper , the structural integrity of the SMALL aspect ratio tokamak (SMART) has been evaluated during normal and off-normal operations in phase 3, and the structural assessment of the vacuum vessel has been performed in order to verify its integrity.
References
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TL;DR: The understanding and predictive capability of transport physics and plasma confinement is reviewed from the perspective of achieving reactor-scale burning plasmas in the ITER tokamak, for both core and edge plasma regions.
Journal ArticleDOI
Equilibrium analysis of current profiles in tokamaks
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Helical temperature perturbations associated with tearing modes in tokamak plasmas
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