Heat loads on the tungsten divertor targets in the ITER and the tokamak power reactors
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …

A future fusion reactor is expected to have all-metal plasma facing materials (PFMs) to
ensure low erosion rates, low tritium retention and stability against high neutron fluences. As …

The JET hybrid scenario has been developed from low plasma current carbon wall
discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the …

The findings of the EU 'Materials Assessment Group'(MAG), within the 2012 EU Fusion
Roadmap exercise, are discussed. MAG analysed the technological readiness of structural …

Detachment of high power discharges is obtained in ASDEX Upgrade by simultaneous
feedback control of core radiation and divertor radiation or thermoelectric currents by the …

Abstract The JET ITER-Like Wall experiment (JET-ILW) provides an ideal test bed to
investigate plasma-surface interaction (PSI) and plasma operation with the ITER plasma …

The behaviour of tungsten in the core of hybrid scenario plasmas in JET with the ITER-like
wall is analysed and modelled with a combination of neoclassical and gyrokinetic codes. In …

JET experiments using the fuel mixture envisaged for fusion power plants, deuterium and
tritium (D–T), provide a unique opportunity to validate existing D–T fusion power prediction …

Future fusion reactors require a safe, steady state divertor operation. A possible solution for
the power exhaust challenge is the detached divertor operation in scenarios with high …

Experimental evidence for the impact of a region of high density localised in the high-field
side scrape-off layer (the HFSHD) on plasma confinement is shown in various dedicated …