Based on experimental observations using the TUMAN-3M and FT-2 tokamaks, and the results of gyrokinetic modeling of the interplay between turbulence and the geodesic acoustic mode (GAM) in these installations, a simple model is proposed for the analysis of the conditions required for L-H transition triggering by a burst of radial electric field oscillations in a tokamak. In the framework of this model, one-dimensional density evolution is considered to be governed by an anomalous diffusion coefficient dependent on radial electric field shear. The radial electric field is taken as the sum of the oscillating term and the quasi-stationary one determined by density and ion temperature gradients through a neoclassical formula. If the oscillating field parameters (amplitude, frequency, etc) are properly adjusted, a transport barrier forms at the plasma periphery and sustains after the oscillations are switched off, manifesting a transition into the high confinement mode with a strong inhomogeneous radial electric field and suppressed transport at the plasma edge. The electric field oscillation parameters required for L-H transition triggering are compared with the GAM parameters observed at the TUMAN-3M (in the discharges with ohmic L-H transition) and FT-2 tokamaks (where no clear L-H transition was observed). It is concluded based on this comparison that the GAM may act as a trigger for the L-H transition, provided that certain conditions for GAM oscillation and tokamak discharge are met.
Ion cyclotron emission (ICE) observation in neutral beam injection (NBI)-heated plasma in the TUMAN-3M tokamak is reported. Experiments were performed in deuterium or hydrogen target plasmas, with the neutral heating beam consisting of 60% deuterium and 40% hydrogen atoms accelerated up to 16 keV. High-frequency internal magnetic probes were used as a diagnostic tool for ICE detection. In deuterium plasmas, emission with ~13 MHz frequency was observed, with 1–2 ms delay after the NBI pulse front; this frequency corresponds approximately to fundamental ion cyclotron (IC) resonance for hydrogen near the magnetic axis. In hydrogen plasmas, ICE with frequency ~7 MHz was observed. In both cases, the observed frequency scales as IC resonance of minority ions. In deuterium plasmas, the hydrogen minority ICE spectral line was found to consist of several narrow (width ~ 50 kHz) spectral components, typically three or more, with different spacing (of the order of 50–200 kHz), and temporal dynamics in synchronicity with sawtooth oscillations. The ICE with the frequency corresponding to IC resonance for majority ions was also observed in several hydrogen and deuterium discharges. Theoretical models developed for the explanation of NBI ICE on other tokamaks are not easily applicable for the phenomena observed on the TUMAN-3M. In pure ohmically heated deuterium and hydrogen plasmas, i.e. in the absence of fast ions, a weak ICE was also observed, with frequency scaling as IC resonance condition in close proximity to the probe location.
The behaviour of the fast particle population during 18 keV hydrogen and 26 keV deuterium neutral beam injection in deuterium plasmas is investigated. Experiments reveal large fast ion losses. The experimental results are confirmed using different types of modelling: simulation using the NUBEAM module, solution of the Boltzmann kinetic equation and solution of the 3D fast ion tracking algorithm. The dynamics of the energetic particle redistribution and losses during sawtooth oscillation and toroidal Alfvén eigenmodes are studied. A method to decrease fast ion losses under the current conditions (0.4 T, 0.2 MA) is shown. The influence of the plasma parameters on the energetic ion confinement rate is investigated. Modelling for the Globus-M2 conditions (1 T, 0.5 MA) is performed.
The existing Globus-M machine [1] is a low aspect ratio compact tokamak (R = 0.36 m, a = 0.24 m) with high specific ohmic and auxiliary heating power. First plasma was achieved in Globus-M in 1999. The machine has demonstrated practically all of the project objectives ever since. Target design parameters (aspect ratio-1.5, 2 − X-point configuration, vertical elongation-2.2, traiangularity-0.45, average density-1.0•10 20 m −3 , plasma current-0.3 MA, toroidal beta-12%, auxiliary heating power-1 MW) [2] were achieved and some of them overcame [3,4]. Also Globus-M
The targeted plasma parameters of the compact spherical tokamak (ST) Globus-M have basically been achieved. The reasons that prevent further extension of the operating space are discussed. The operational limits of Globus-M together with an understanding of the limiting reasons form the basis for defining the design requirements for the next-step, Globus-M2. The recent experimental and theoretical results achieved with Globus-M are discussed, the operational problems and the research programme are summarized and finally, the targeted Globus-M2 parameters are presented. The magnetic field and plasma current in Globus-M2 will be increased to 1 T and 0.5 MA, respectively. The plasma dimensions will remain unchanged. With auxiliary heating at a high average plasma density, the temperatures will be in the keV range and the collisionality parameter with ν * 1 will define the operational conditions. Noninductive current drive will be a major element of the programme. The engineering design issues of Globus-M2 tokamak are discussed and the technical tokamak parameters are confirmed by thermal load and stress analysis simulations. The experimental results obtained on Globus-M2 and the limits of its performance should clarify the feasibility of an ST-based super compact neutron source.
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