Plasma disruption is one of the major challenges for ITER. A large fraction of runaway
current may be formed due to the avalanche generation of runaway electrons (REs) in …

Disruption is one of the urgent problems for future tokamaks in possibly causing heat loads,
halo currents, and runaway electrons (REs). Massive impurity injection is a feasible way to …

This paper introduces the first results of deuterium retention on the Experimental Advanced
Superconducting Tokamak (EAST) using particle balance. In the fall 2010 EAST …

Behaviors of impurity and hydrogen recycling are investigated based on passive
spectroscopy measurement on HT-7. During LHCD long pulse discharges, impurity and …

Runaway Electrons (REs) generated during plasma disruptions in fusion grade tokamaks
have the potential to severely damage the plasma-facing components. Designing optimal …

To study the effects of different mitigation strategies on the RE beam generated in a
COMPASS tokamak discharge [3], a calorimetry probe was developed as one of the relevant …

Control of fuel recycling and hydrogen content in the Experimental Advanced
Superconducting Tokamak (EAST) using various methods is studied for high-power long …

An overview of steady state tokamak studies in TRIAM-1M (R 0= 0.8 m, a× b= 0.12 m× 0.18
m and B= 8 T) is presented. The current ramp-up scenario without using centre solenoid …

The natural density (plasma density without gas puffing) of an ELMy H-mode discharge is
strongly affected by fuel recycling and plasma parameters. In the EAST 2012 campaign fuel …

The lithium and boron powder have been successfully real-time injected into Experimental
Advanced Superconducting Tokamak (EAST) high-confinement (H−) mode discharges …