One of the critical challenges for long pulse operation of ITER and future fusion reactors is
the excessively high heat and particle fluxes on the divertor targets. The divertor detachment …

Divertor detachment of high N b H-mode discharges has been achieved by the injection of
radiating impurities in the very closed divertor geometry of HL-2A. Non-intrinsic impurity is …

Multi-species impurity seeding is an advanced operation scenario to mitigate the divertor
heat load for the realization of future fusion reactors. In the large helical device, divertor …

Radiative divertor is an effective method for the divertor heat flux control, but excessive core
impurity radiation can deteriorate the confinement in tokamaks. In recent EAST experiments …

The first stable completely detached H-mode plasma in the full tungsten ASDEX Upgrade
has been achieved. Complete detachment of both targets is induced by nitrogen seeding …

Burning plasmas with 500 MW of fusion power on ITER will rely on partially detached
divertor operation to keep target heat loads at manageable levels. Such divertor regimes will …

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 …

The external Ne impurity seeding has been applied to reduce the heat flux to the divertor
target as well as plasma temperature to prolong the lifetime of the EAST upper tungsten (W) …

Since the last IAEA-Fusion Energy Conference, the Experimental Advanced
Superconducting Tokamak (EAST) research program has been, in support of ITER and …

Divertor tungsten (W) erosion source during edge localized mode (ELM) bursts in EAST is
investigated based on optical emission spectroscopy on atomic neutral tungsten line …