Abstract Following the IAEA Technical Meeting on'Advanced Methodologies for the Analysis
of Materials in Energy Applications Using Ion Beam Accelerators', this paper reviews the …

JET underwent a transformation from a full carbon-dominated tokamak to a fully metallic
device with beryllium in the main chamber and a tungsten divertor. This material …

The WEST project recently launched at Cadarache consists in transforming Tore Supra in an
X-point divertor configuration while extending its long pulse capability, in order to test the …

The ITER divertor design is the culmination of years of physics and engineering effort,
building confidence that this critical component will satisfy the requirements and meet the …

The residual carbon content and carbon edge flux in JET have been assessed by three
independent diagnostic techniques after start of plasma operation with the ITER-Like Wall …

It is estimated that pilot plants and reactors may experience rates of net erosion and
deposition of solid plasma facing component (PFC) material of 10 3–10 5 kg yr− 1. Even if …

Tritium self-sufficiency is a critical issue for the production of nuclear fusion energy. Here we
quantify the impact of co-deposition of eroded wall material and fuel on the tritium particle …

W7-X completed its plasma operation in hydrogen with island divertor and inertially cooled
test divertor unit (TDU) made of graphite. A substantial set of plasma-facing components …

The steady-state criterion for plasma numerical simulations can be determined by the
particle balance relation. In this study, we utilized a one-dimensional (1D) particle-in …

Abstract Wendelstein 7-X (W7-X) is an optimized stellarator with a 3-dimensional five-fold
modular geometry. The plasma-wall-interaction (PWI) investigations in the complex 3D …