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...

Nuclear fusion energy is an ideal source for the future due to clean and efficient features, first proposed by Russian scientists in 1950s. With successful construction operation of a batch tokamak devices globally, series major achievements have been realized magnetic confinement (MF). On this basis, recent progress current status are systematically reviewed from academic literatures official ...

Abstract The physics governing the collisional transport of impurities in tokamak plasmas can change significantly depending on four main parameters, namely collisionality, impurity charge and mass, trapped particle fraction, which vary widely from core to edge a fusion device. We present an analytical model for with consistent dependence broad scans these showing good agreement drift-kinetic c...

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...

Transient coaxial helicity injection (T-CHI), a method first developed on the small injected torus (HIT-II) experiment and then validated much larger National Spherical Torus Experiment (NSTX) device, is to initiate an inductive-like tokamak plasma discharge without reliance central solenoid. A CHI initiated by driving current along magnetic flux that connects inner outer divertor plates one en...

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The structure of magnetic field lines in a tokamak with reversed magnetic shear is investigated by means of analytically derived area-preserving non-twist Poincaré maps. The basic configuration is the magnetic field produced by an ergodic limiter, superimposed to the tokamak equilibrium field in suitable coordinates. We consider the cases of one and two resonant modes, focusing on magnetic isla...

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The particle and energy transport was analyzed for different regions and regimes of the plasma in tokamak with special attention for ITER. For the particle transport in the tokamak edge plasma was obtained results useful for the qualitative cross-check of the numerical models of the first principle simulations, including ITER, as well as in the elaboration of the simplified, reduced models of t...