Abstract The Experimental Advanced Superconducting Tokamak (EAST) research program
concentrates on demonstrating steady-state high-performance H-mode operations with ITER …

ELM mitigation to avoid melting of the tungsten (W) divertor is one of the main factors
affecting plasma fuelling and detachment control at full current for high Q operation in ITER …

The active feedback control of radiated power to prevent divertor target plates overheating
during long-pulse operation has been developed and implemented on EAST. The radiation …

Compatibility of dissipative divertor operation with a robust H-mode pedestal has been
examined in DIII-D. The pedestal density profile is found to respond to changes in fueling …

Systematic investigations of gas fuelled, high density H mode discharges with the new
closed Divertor II of ASDEX Upgrade are reported. The focus is on operational limits (HL …

Nuclear fusion is one of the few future energy sources that has the potential to fulfill
increasing energy demands whilst remaining virtually inexhaustible, inherently safe, and …

The impurity-seeded detached divertor is essential for heat exhaust in ITER and other
reactor-relevant devices. Dedicated experiments with injection of N 2, Ne and Ar have been …

H-mode discharges with lower hybrid current drive (LHCD) alone are achieved in EAST
divertor plasma over a wide parameter range. These H-mode discharges are characterized …

Divertor detachment regime is required for the future tokamak device operation. The
radiative divertor with neon-impurity seeding on EAST tokamak is studied by using SOLPS …

The main objective of this paper is investigation of methods for reduction of divertor heat
loads in order to increase the lifetime of divertor tiles in future fusion reactors. Special …