Newly uncovered physics of MHD instabilities using 2-D electron cyclotron emission imaging system in toroidal plasmas

Validation of physics models using the newly uncovered physics with a 2-D electron cyclotron emission imaging (ECEi) system for magnetic fusion plasmas has either enhanced the confidence or substantially improved the modeling capability. The discarded "full reconnection model" in sawtooth instability is vindicated and established that symmetry and magnetic shear of the 1/1 kink mode are critical parameters in sawtooth instability. For the 2/1 instability, it is demonstrated that the 2-D data can determine critical physics parameters with a high confidence and the measured anisotropic distribution of the turbulence and its flow in presence of the 2/1 island is validated by the modelled potential and gyro-kinetic calculation. The validation process of the measured reversed-shear Alfveneigenmode (RSAE) structures has improved deficiencies of prior models. The 2-D images of internal structure of the ELMs and turbulence induced by the resonant magnetic perturbation (RMP) have provided an opportunity to establish firm physics basis of the ELM instability and role of RMPs. The importance of symmetry in determining the reconnection time scale and role of magnetic shear of the 1/1 kink mode in sawtooth instability may be relevant to the underlying physics of the violent kink instability of the filament ropes in a solar flare

High-resolution disruption halo current measurements using Langmuir probes in Alcator C-Mod

Halo currents generated during disruptions on Alcator C-Mod have been measured with Langmuir “rail” probes. These rail probes are embedded in a lower outboard divertor module in a closely-spaced vertical (poloidal) array. The dense array provides detailed resolution of the spatial dependence (~1 cm spacing) of the halo current distribution in the plasma scrape-off region with high time resolution (400 kHz digitization rate). As the plasma limits on the outboard divertor plate, the contact point is clearly discernible in the halo current data (as an inversion of current) and moves vertically down the divertor plate on many disruptions. These data are consistent with filament reconstructions of the plasma boundary, from which the edge safety factor of the disrupting plasma can be calculated. Additionally, the halo current “footprint” on the divertor plate is obtained and related to the halo flux width. The voltage driving halo current and the effective resistance of the plasma region through which the halo current flows to reach the probes are also investigated. Estimations of the sheath resistance and halo region resistivity and temperature are given. This information could prove useful for modeling halo current dynamics

Modeling synchrotron radiation images of runaway electrons

One of the most powerful means of studying runaway electrons in tokamaks is by measuring the synchrotron radiation they emit. In many current experiments, visible light and IR cameras are used to study the synchrotron radiation spot, and spectrometers measure the synchrotron radiation spectrum. Due to the strong dependence on the particle energy, pitch angle and radial position in both the synchrotron spot and spectrum, these can be used to extract valuable information about the runaway electron distribution function. Obtaining accurate information about the runaway electron distribution function from synchrotron radiation measurements however, requires both the magnetic field, camera location and camera spectral range to be handled properly and taken into account. In this contribution we present the synthetic synchrotron diagnostic SOFT (Synchrotron-detecting Orbit Following Toolkit) which simulates the synchrotron radiation from a population of runaway electrons whose energy, pitch angle and radial location are known in the outer midplane. By following the guiding-center orbits of the population, effects arising due to the inhomogeneity of the magnetic field are incorporated, which we show have significant effects on both the synchrotron radiation spot and spectrum.As an application of SOFT, we try to reproduce asynchrotron image from one discharge in the Alcator C-Mod tokamak. By taking measured parameters of the Alcator C-Mod discharge, a distribution function is obtained with the Fokker-Planck solver CODE, for which the emitted synchrotron radiation can then be simulated in SOFT, which shows good agreement. With SOFT, an interpretation for the synchrotron radiation spot observed in experiment can be given, and the characteristic comet shape of the Alcator C-Mod synchrotron radiation spot is shown to be the result of the vertical placement of the camera, together with the narrow set of pitch angles possessed by the particles, as well as their radial distribution

Feasibility study for a high-k temperature fluctuation diagnostic based on soft x-ray imaging

A new pseudolocal tomography algorithm is developed for soft X-ray(SXR) imaging measurements of the turbulent electron temperature fluctuations (δ Te) in tokamaks and stellarators. The algorithm overcomes the constraints of limited viewing ports on the vessel wall (viewing angle) and limited number of lines of sight (LOS). This is accomplished by increasing the number of LOS locally in a region of interest. Numerical modeling demonstrates that the wavenumber spectrum of the turbulence can be reliably reconstructed, with an acceptable number of viewing angles and LOS and suitable low SNR detectors. We conclude that a SXR imaging diagnostic for measurements of turbulent δ Te using a pseudolocal reconstruction algorithm is feasible

beta limiting MHD activity and mode locking in Alcator C-Mod

Since Alcator C-Mod normally operates at high toroidal field and high collisionality, beta limiting instabilities are rarely observed. Under some conditions, however, when operating at low collisionality and high input power (P-ICRF less than or equal to 5 MW), large amplitude (5 x 10(-5) 0.52 and increased in amplitude with increasing beta until a rollover or collapse in beta occurred. The largest amplitude modes with m = 2, n = 1 strongly degraded momentum and energy confinement when the modes coupled across the plasma core and locked to the wall, bringing the plasma ion toroidal rotation to zero, within experimental errors, about 50 ms after mode locking. MHD stability was calculated with the linear resistive toroidal MHD code MARS for a discharge with a large m = 2, n = 1 mode. Comparisons with neoclassical tearing mode (NTM) theory and with NTMs found on other tokamaks indicate that these modes may be driven by a combination of resistive, neoclassical, and error field effects

Measurements of the high confinement anode pedestal region on Alcator C-Mod

Measurements of the steep transport barrier at the edge of the Alcator C-Mod tokamak [1. H. Hutchinson et at., Phys. Plasmas 1, 1511 (1994)] are presented. The parameters at the top of this barrier are in the range T-e=150-750 eV and n(e)=0.5-3.3x10(20) m(-3), depending on the confinement regime. Type m edge localized modes (ELMs) have an upper temperature limit. T-e pedestal profiles show a barrier width Delta similar or equal to=8 mm. Soft x-ray emissivity profiles are narrower, with Delta=2-4 mm. Edge currents are calculated to alter the ideal stability boundary favorably, leading to ideally stable pedestal profiles. High frequency, broadband, edge density fluctuations are sometimes observed in H-mode (high-confinement mode) and are associated with enhanced particle transport. Coherent magnetic fluctuations localized near the pedestal are also seen

Double transport barrier experiments on Alcator C-Mod

Double transport barrier modes (simultaneous core and edge transport barrier) have been observed with off-axis ion cyclotron range of frequencies (ICRF) heating in the Alcator C-Mod tokamak [I. H. Hutchinson , Phys. Plasmas 1, 1511 (1994)]. An internal transport barrier (ITB) is routinely produced in enhanced DalphaH-mode (EDA) discharges where the minority ion cyclotron resonance layer is at r/asimilar to\0.5\ during the current flat top phase of the discharge. The density profile becomes peaked without the presence of a particle source in the plasma core and continues to peak until the increased core impurity radiation arrests the improved energy confinement, ultimately leading to a barrier collapse. With the addition of moderate (0.6 MW) central ICRF heating, the double barrier mode was maintained for as long as the ICRF power was applied. Modeling shows that the internal thermal barrier was maintained throughout the discharge. The presence of sawteeth throughout most of the ITB discharge allows sawtooth-induced heat pulse analysis to be performed. This analysis indicates that there is an abrupt radial discontinuity in the heat pulse time to peak profile when an ITB is present. Furthermore, this discontinuity appears to move into the core plasma from the edge region in about 0.2 s, several confinement times. The deduced thermal diffusivity, chi(hp), indicates that a barrier exists in the electron thermal transport, the barrier is limited to a narrow radial region, and the transport is unaffected outside this narrow radial extent

Chapter 3: MHD stability, operational limits and disruptions

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