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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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Internal magnetic field measurements by laser-based POlarimeter-INTerferometer (POINT) system on EAST

TL;DR: In this paper, a multi-channel far-infrared laser-based POlarimeter-INTerferometer (POINT) system utilizing the three-wave technique has been implemented for fully diagnosing the internal magnetic field in the EAST tokamak.
Journal ArticleDOI

Ideal MHD stability and performance of ITER steady-state scenarios with ITBs

TL;DR: In this paper, the authors present non-inductive scenario simulations with five combinations of heating and current drive sources, with plasma currents in the range 7-10 MA, and the linear, ideal MHD stability is analyzed for variations of the Greenwald fraction and of the pressure peaking factor around the operating point, aiming at defining an operational space for stable, steady state operations at optimized performance.
Journal ArticleDOI

Plasma profile evolution during disruption mitigation via massive gas injection on MAST

TL;DR: In this article, the penetration of the injected impurities during MGI in MAST is diagnosed using a combination of high-speed (20?kHz) visible imaging and high spatial (1?cm) and temporal (0.1?ms) resolution Thomson scattering (TS) measurements of the plasma temperature and density.
Journal ArticleDOI

Passive runaway electron suppression in tokamak disruptions

TL;DR: In this article, it was shown that it is difficult to ergodize the central plasma before a beam of runaway current has formed, which can lead to instabilities that yield large runaway electron losses.
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Deployment of multiple shattered pellet injection systems in KSTAR

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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.
Journal ArticleDOI

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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