The heating of tungsten monoblocks at the ITER divertor vertical targets is calculated using
the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are …

The provision of a particle and power exhaust solution which is compatible with first-wall
components and edge-plasma conditions is a key area of present-day fusion research and …

The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles,
determines the lifetime of plasma-facing components as well as impacting on plasma …

Drift ordered fluid models are widely applied in studies of low-frequency turbulence in the
edge and scrape-off layer regions of magnetically confined plasmas. Here, we show how …

An efficient removal of He ash by active pumping in future fusion devices is necessary to
avoid fuel dilution and not degrade the core confinement properties. Therefore, a deep …

The ITER baseline scenario, with 500 MW of DT fusion power and Q= 10, will rely on a Type
I ELMy H-mode, with ΔW= 0.7 MJ mitigated edge localized modes (ELMs). Tungsten (W) is …

Retention of hydrogen isotopes (HI) in plasma-facing components (PFCs) is a crucial
process influencing the operation of a fusion device. The dynamics of HI retention is mainly …

The dynamics and stability of divertor detachment in ${{\rm {N}}} _ {2} $ seeded, type-I, ELMy
H-mode plasmas with dominant NBI heating in the JET ITER-like wall device is studied by …

Abstract Analysis of the divertor edge localized mode (ELM) electron temperature at a
uniquely high temporal resolution (10− 5 s) was reported at the JET tokamak (Guillemaut et …

The ITER baseline scenario, with 500 MW of DT fusion power and Q= 10, will rely on a Type
I ELMy H-mode and will be achieved with a tungsten (W) divertor. W atoms sputtered from …