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 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 …

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 …

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 …

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 …

The neoclassical transport optimization of the Wendelstein 7-X stellarator has not resulted in
the predicted high energy confinement of gas fueled electron-cyclotron-resonance-heated …

Since the last IAEA Fusion Energy Conference in 2018, significant progress of the
experimental program of HL-2A has been achieved on develo** advanced plasma …