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Chapter 3: MHD stability, operational limits and disruptions

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TLDR
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.

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Citations
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Analysis of Electromagnetic Forces in Tokamak Vacuum Chamber due to Induced Poloidal Current after Thermal Quench

TL;DR: In this paper, the influence of poloidal current induced in a tokamak vacuum chamber due to change of paramagnetic plasma properties as a result of thermal quench on the magnitude and distribution of electromagnetic forces in a vacuum chamber was studied.
Journal ArticleDOI

Error Field Impact on Plasma Boundary in ITER Scenarios

TL;DR: In this article, the effect of EFs on the plasma boundary shape during the shot, modeled as a sequence of equilibrium configurations, was analyzed using high accuracy 3D magnetic field computations for confinement coils.
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Plasma-resistivity-induced strong destabilization of the kinetic resistive wall mode

V. V. Yanovskiy
- 20 Oct 2016 - 
TL;DR: In this article, it was shown that the plasma resistivity can have a strong impact on the stability of resistive wall modes (RWMs), and the stability criteria for kinetic RWMs derived in Hu and Betti [Phys. Rev. Lett. 93, 105002 (2004)] has been complemented by the restriction on the maximum mode damping rate.
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Comparison of a fast low spatial resolution inversion method and peaking factors for the detection of anomalous radiation patterns and disruption prediction

TL;DR: In this paper , a fast tomographic algorithm was proposed to detect and classify anomalous radiation patterns, such as core radiation and MARFEs, and to predict upcoming electron temperature anomalies with much better accuracy and reliability than using simple peaking factors.
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Numerical simulation of the effect of pellet injection on ELMs

TL;DR: In this paper, the authors report on numerical simulation studies of the dynamical behavior of edge localized modes (ELMs) under the influence of repetitive injection of pellets and find that when the edge density is raised to twice the normal edge density with a duty cycle (on time:off time) of 1:2, the ELMs are generated on an average at a faster rate and with reduced amplitudes.
References
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Journal ArticleDOI

Chapter 1: Overview and summary

David Campbell
- 01 Dec 1999 - 
TL;DR: The ITER Physics Basis as mentioned in this paper presents and evaluates the physics rules and methodologies for plasma performance projections, which provide the basis for the design of a tokamak burning plasma device whose goal is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes.
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Equilibrium analysis of current profiles in tokamaks

TL;DR: In this paper, an efficient method is given for self-consistent reconstruction of the tokamak current profiles and their associated magnetic topology using the magnetohydrodynamic (MHD) equilibrium constraint from external magnetic measurements, kinetic profile measurements, internal poloidal magnetic field measurements, and topological information from soft X-ray (SXR) measurements.
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Helical temperature perturbations associated with tearing modes in tokamak plasmas

TL;DR: In this article, an investigation into the electron temperature perturbations associated with tearing modes in tokamak plasmas was made, and it was found that there is a critical magnetic island width below which the conventional picture where the temperature is flattened inside the separatrix is invalid.
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