The Japan Atomic Energy Research Institute (JAERI) completed the divertor modification of
the JAERI Tokamak-60 Upgrade (JT-60U)[Y. Koide and the JT-60 Team, Phys. Plasmas 4 …

To obtain a quantitative understanding of the recent radiative divertor experiments and to
give an instructive prediction for the future relative work performed on EAST, the 2D …

The aim of this paper is to estimate the effects of usual drifts and gas puffing/pumping
locations on divertor detachment and Ar ion transport in the Experimental Advanced …

Recent progress towards an increased understanding of detached divertor physics has
been made with the highly closed divertor geometry in HL-2A. Non-intrinsic impurities were …

Reduction of divertor heat load is a crucial issue for next generation fusion reactors such as
ITER [1] and DEMO [2]. Plasma operation with detached divertors is considered to be a …

Reduction in the power load deposited onto the divertor target plates is achieved with
supersonic molecular beam injection (SMBI) fuelling. The largest reduction in the heat flux …

The scientific and the engineering missions of EAST are to explore the reactor related
regimes with long pulse lengths and high plasma core confinement and solutions for power …

Impurity seeding is being investigated in present tokamaks as a technique for divertor heat
load mitigation by radiating exhaust power from the plasma, which has application to future …

H-mode access will be required from the early stages of ITER operation onwards to develop
plasma scenarios and test control techniques (ELM mitigation, H-mode exit). Knowledge of …

ITER or any other future fusion device will operate in H-mode to take advantage of the
improved confinement. Stationary operation in H-mode, however, requires the occurrence of …