Theoretical and experimental investigations of stochastic boundaries in tokamaks

Abstract

This review paper addresses the physics of stochastic boundaries. Although it is focused on the tokamak configuration many features are common to the stochastic boundaries of stellarators. The stochastic properties of magnetic field lines are recalled and related to the spectrum of the radial magnetic perturbation. The stochastic region, referred to as the divertor volume, is shown to be bounded to the edge plasma. Furthermore, the stochastic features discriminate two regions. On short scales, the stochasticity is not effective and parallel transport dominates, this defines the laminar region. On the long scales one recovers the proper stochastic features which characterize the ergodic regime. Theoretical predictions for the transport of energy, current and particles in the divertor volume are analysed for both the laminar and ergodic regimes. A strong increase in electron transport is expected which should lead to a strong increase in the heat diffusivity, a strong increase in the resistivity in the toroidal direction and generally a decrease in the free electron lifetime in the divertor volume. Ambipolarity of particle transport is ensured by a radial electric field. The ion transport, i.e. particle transport, is then more difficult to analyse since one has to consider the strong coupling to the electron temperature field and to the electric potential field. The perturbation level is such that the particle transport induced by the stochasticity remains comparable to the anomalous transport. The experimental data show good agreement with the predictions on electron transport. This translates into a flattening of the edge temperature gradient, a narrowing of the current channel, which probably governs the observed stabilization of MHD activity, and a strong decrease in the lifetime of the runaway electrons. Regarding particle transport, the response is larger than expected and stochastic boundaries are characterized by significant screening properties compared to limiter shots. This property is shown to be a signature of a pumping capability combined with a change of transport properties. Indeed the transport of neutrals is changed since the ratio of the ionization scales to the distance between the recycling surfaces and the separatrix is reduced. Furthermore, a decreased lifetime of the ions at the very edge of the plasma is expected. Screening effects are thus observed for species exhibiting large wall pumping capability, while He and Ne are weakly affected by the stochastic boundary. The plasma properties in the ergodic volume, namely a reduced edge temperature, an increased impurity radiation, an efficient particle screening and the stabilization of MHD activity, have opened the way to radiating layer investigations on Tore Supra. Stable operation has been achieved with 80% of radiated power and radio frequency heating up to 6 MW.

Fractal structure of the magnetic field in the laminar zone of the Dynamic Ergodic Divertor of the Torus Experiment for Technology-Oriented Research (TEXTOR-94)

“…The changes of the plasma regime can be also produced by varying the magnetic field B t at the fixed plasma current. However, one should note that for the two magnetic equilibria 2) ) which have the same resonant magnetic surfaces r mn , the plasma edge will be affected more strongly in the case with the smaller toroidal magnetic field B t ϭmin(B t (1) ,B t…”

Modelling with the 2D multifluid code TECXY of TEXTOR discharges in the presence of DED

“…As experimentally shown by the Ergodic Divertor in the tokamak Tore Supra [19] and theoretically predicted [20], at the onset of the perturbing radial field of the DED one might expect an increase of carbon screening and an increase of the ratio of total radiated power to impurity density in the plasma core. On TEXTOR the location of C +2 ions originated from ionization of C +1 is very close to the carbon source both in poloidal and radial directions.…”

Characteristics of local helical coil system for dynamic ergodic divertor

“…A large number of studies have been performed in several tokamak devices to investigate this innovative concept for advanced tokamaks. In these experiments, however, a nonuniform distribution of plasma parameters near the perturbation coils was found [2]. This nonuniformity comes from the poloidal nonuniformity of the magnetic structure near the perturbation coils, and it causes localization of the heat load to the wall.…”

“…The second problem imposed by steady-state operation is particle control. It is necessary (1) to control the recycling of fuel particles, (2) to prevent the impurity particles from penetrating into the core region, and (3) to remove helium ash. The Ergodic Divertor (ED) is one scheme for controlling the particle and heat flux in tokamaks.…”