Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999
Nucl. Fusion 39 2137–2664), in understanding the processes that will determine the …

The understanding and predictive capability of transport physics and plasma confinement is
reviewed from the perspective of achieving reactor-scale burning plasmas in the ITER …

This paper presents recent activities covering different plasma fields, from both theoretical
and experimental point of views. An overview of the present interests of the scientific …

Operating ITER in the reference inductive scenario at the design values of I p= 15 MA and Q
DT= 10 requires the achievement of good H-mode confinement that relies on the presence …

Feedback control of the divertor power load by means of nitrogen seeding has been
developed into a routine operational tool in the all-tungsten clad ASDEX Upgrade tokamak …

With increasing size of a tokamak device and associated fusion power gain an increasing
power flux density towards the divertor needs to be handled. A solution for handling this …

Tungsten erosion in the outer divertor of the JET ITER like wall was quantified by
spectroscopy. Effective sputtering yields of typically 10− 4 were measured in L-mode at∼ …

Divertor detachment may be essential to reduce heat loads to magnetic fusion tokamak
reactor divertor surfaces. Yet in experiments it is difficult to control the extent of the detached …

New experimental results on transient loads during ELMs and disruptions in present divertor
tokamaks are described and used to carry out a extrapolation to ITER reference conditions …

With tokamak devices developing towards higher heating powers, and carbon plasma facing
components being increasingly replaced by high-Z materials like tungsten, impurity seeding …