Experiments on FTU with a liquid lithium limiter

During the year 2007, experiments have been carried on to test a Liquid Lithium Limiter (LLL) with capillary porous system (CPS) on the high field medium size tokamak FTU. Previous results [1] with LLL have shown that plasma discharges with lithized walls are remarkably cleaner than those with purely metallic or boronized ones: Zeff in ohmi

Parametric calculations of the first wall thermal response during plasma disruptions for the NET

Associazione EURATOM - ENEA sulla fusione. Progetto ENEA: Ingegneria del reattore a fusione (DC)SIGLEITItal

Radial particle flow, electrical-conductivity and thermal-energy content in the Frascati Tokamak upgrade

Experimental determinations of the radial plasma flow velocity, of Z(eff) and of the thermal energy content, made on the Frascati Tokamak Upgrade (FTU), have been compared with the predictions of the conventional neoclassical theory, of the extended neoclassical theory and of the pseudoneoclassical theory. In the comparison only the momentum balance and continuity equations were used. The best overall agreement is found for the second of these theories, thus confirming the result of previous analyses

The Ignitor Diagnostic Systems

The scientific objectives of Ignitor, centered on the study of fusion burning plasmas, lead to a choice of diagnostic systems that give priority to those objectives and have a special set of characteristics. These systems have to withstand large fluxes of neutrons and γ-rays which are produced in the surrounding materials. This hostile radiation environment introduces new problems, like radiation induced background and permanent damage to components such as detectors and electronics. The selection of diagnostics tools for an ignition experiment should therefore be based on a set of strict rules. All diagnostics must have a high degree of reliability; a straight line of sight plasma-detector should be avoided as much as possible, and instruments must allow the placement of the detection section at a safe distance from the plasma where it can be properly shielded. A set of important diagnostic systems satisfying these criteria are discusse

MHD and confinement during pellet injection on FTU

The study sets out to investigate the parts of the FTU operating space over which pellet injection effects performance improvement and to elucidate the phenomena which hinder it. In this respect the behaviour of the q=1 resonance is found to play the most relevant role

Plasma characteristics in FTU with different plasma facing materials

Experiments with different dominant impurities (C, Si, Ni, Mo) have been carried out on the FTU tokamak. Density limit, marfe, Zeff and radiation losses are compared and discussed. An analytical model that couples in a self consistent way the parameters of the SOL and the transport of the impurities generated at the limiter to the bulk plasma parameters has been used to reproduce the experimental data