A previously published magnetohydrodynamical MHD model of error-field penetration in tokamak plasmas is extended to take drift-MHD physics into account. In particular, diamagnetic and semicollisional effects are both fully incorporated into the analysis. The new model is used to examine the scaling of the penetration threshold in ohmic tokamak plasmas. © 2006 American Institute of Physics. DOI:...

This subgroup of the Magnetic Fusion Concepts Working Group discussed the plans for developing the major magnetic confinement concepts: standard pulsed tokamak, advanced tokamak, spherical torus, compact stellarator, reversed-field pinch, and spheromak The goal was to identify, for each concept, what understanding and capability must be developed to establish its basis for a useful magnetic fus...

The next major frontier in magnetic fusion physics is to explore and understand the strong non-linear coupling among confinement, MHD stability, self-heating, edge physics and waveparticle interactions that is fundamental to fusion plasma behavior. The Fusion Ignition Research Experiment (FIRE) design study has been undertaken to define the lowest cost facility to attain, explore, understand an...

Semiconductor detector arrays are widely used in high-temperature plasma diagnostics. They have a fast response, which allows observation of many processes and instabilities in tokamaks. In this paper, there are reviewed several diagnostics based on semiconductor arrays as cameras, AXUV photodiodes (referred often as fast “bolometers”) and detectors of both soft X-rays and visible light install...

Introduction During the last years, significant progress was made in the control of resistive wall modes (RWMs) in reversed field pinches (RFPs). It was demonstrated on several different devices that static current driven RWMs can be completely suppressed and controlled [1,2]. It is well known that also tokamak advanced scenarios suffer from RWM instabilities. The RWM in a tokamak is typically ...

The control of plasma in nuclear fusion has been revealed as a promising application of Control Engineering, with increasing interest in the control community during last years. In this paper it is outlined a control-oriented linear model for the control of plasma current. For this purpose, it is firstly provided a summary of the background necessary to deal with control problems in tokamak-bas...

The creation of an outer layer of chaotic magnetic field lines in a tokamak is useful to control plasma-wall interactions. Chaotic field lines (in the Lagrangian sense) in this region eventually hit the tokamak wall and are considered lost. Due to the underlying dynamical structure of this chaotic region, namely a chaotic saddle formed by intersections of invariant stable and unstable manifolds...

Providing a historical overview of 50 years of fusion research, a review of the fundamentals and concepts of fusion and research efforts towards the implementation of a steady state tokamak reactor is presented. In 1990, a steady-state tokamak reactor (SSTR) best utilizing the bootstrap current was developed. Since then, significant efforts have been made in major tokamaks, including JT-60U, ex...

28 I n practical terms, the project’s goal is to construct and operate a tokamak experiment which can confine a deuterium-tritium plasma in which the α-particle heating dominates all other forms of plasma heating. Formally, the primary mission of the ITER project is to demonstrate sustainment of a DT plasma producing ~500 MW of fusion power for durations of 300 500 s with a ratio of fusion outp...

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