Abstract

Since the 2012 IAEA-FEC Conference, FTU operations have been largely devoted to runaway electrons generation and control, to the exploitation of the 140 GHz electron cyclotron (EC) system and to liquid metal limiter elements. Experiments on runaway electrons have shown that the measured threshold electric field for their generation is larger than predicted by collisional theory and can be justified considering synchrotron radiation losses. A new runaway electrons control algorithm was developed and tested in presence of a runaway current plateau, allowing to minimize the interactions with plasma facing components and safely shut down the discharges. The experimental sessions with 140 GHz EC system have been mainly devoted to experiments on real-time control of magnetohydrodynamic (MHD) instabilities using the new EC launcher with fast steering capability. Experiments with central EC injection have shown the onset of 3/2 and 2/1 tearing modes, while EC assisted breakdown experiments have been focused on ITER start-up issues, exploring the polarization conversion at reflection from inner wall and the capability to assure plasma start-up even in presence of a large stray magnetic field. A new actively cooled lithium limiter has been installed and tested. The lithium limiter was inserted in the scrape-off layer, without any damage to the limiter surface. First elongated FTU plasmas with EC additional heating were obtained with the new cooled limiter. Density peaking and controlled MHD activity driven by neon injection were investigated at different plasma parameters. A full real-time algorithm for disruption prediction, based on MHD activity signals from Mirnov coils, was developed exploiting a large database of disruptions. Reciprocating Langmuir probes were used to measure the heat flux e-folding length in the scrape-off layer, with the plasma kept to lay on thea internal limiter to resemble the ITER start-up phase. New diagnostics were successfully installed and tested, as a diamond probe to detect Cherenkov radiation produced by fast electrons and a gamma camera for runaway electrons studies. Laser induced breakdown spectroscopy measurements were performed under vacuum and with toroidal magnetic field, so demonstrating their capability to provide useful information on the surface elemental composition and fuel retention in present and future tokamaks, such as ITER.

Highlights

  • FTU is a compact high magnetic field tokamak aimed at developing advanced scenarios at magnetic field and densities relevant to ITER operation, as well as at studying its supporting physics [1]

  • One of the more ITER-relevant issues is to ascertain whether the high density and the electron–ion collisional coupling influence the internal transport barriers (ITBs) dynamics and whether an ion transport barrier could develop in the presence of e− heating only

  • We describe the principal physical effects observed on the plasma behaviour, edge and core, distinguishing between those linked to the lithization and those more strictly caused by the actual presence of the liquid lithium limiter (LLL) in the scrape-off layer (SOL) plasma

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Summary

Introduction

The main heating source will be the α-particles that interact predominantly with electrons, while the toroidal momentum, provided by neutral beam injection (NBI), is remarkably lower than in most present-day tokamaks with NBI as an additional heating source This casts some concern on extrapolating the energy confinement of the advanced scenarios with internal transport barriers (ITBs) to ITER. Since the advanced scenarios are very promising for a steady operation of ITER and future reactors, where the rotational shear will be negligible, the study of ITBs that are built and maintained with dominant electron heating are of particular importance Another crucial aspect for tokamak reactors concerns the best choice of plasma facing components (PFCs). Conclusions are drawn and a brief summary on the work carried out in the years 2005–2006 is given in section 9 together with the near-term perspectives

Advanced tokamak scenarios
Pericoli-Ridolfini et al MW 1020 m–3
Technical achievements with LLL
Effects of the lithized walls
Greenwald limit
Effects of the LLL inside the vacuum vessel
Disruption mitigation with ECH
MHD mode control
LHCD physics study
Theoretical analyses of electron-fishbone dynamics
Findings
Conclusions and perspectives
Full Text
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