Active control of the excessively high heat and particle fluxes on the divertor target plates is
of fundamental importance to the steady state operation of tokamaks, especially for fusion …

A study of the effects of radial transport on the outer divertor particle and power flux widths (λ
js and λ q) is carried out using plasmas under different operational regimes in the …

The new lower tungsten divertor of EAST uses a right-angle shape consisted by horizontal
and vertical targets, which has the capacity of increasing the divertor closure. The strike …

An investigation into tungsten (W) impurity behaviors with the update of the EAST lower W
divertor for H-mode has been carried out using SOLPS-ITER. This work aims to study the …

A study of the effect of toroidal magnetic field (B t) on the divertor asymmetries is carried out
with a plasma transport code under BOUT++ framework with the magnetic equilibria from …

A study of the effects of drifts on the particle flow pattern and in–out divertor plasma density
asymmetry for L-mode and H-mode plasmas is carried out for EAST discharges by the edge …

Prediction of divertor heat flux width is performed for the first and the second pre-fusion
power operation (PFPO) phases specified in the new ITER research plan using BOUT++ …

The divertor operation in the detached plasma regime is necessary to reduce the loads on
the divertor plates in the ITER and DEMO tokamaks to acceptable values. The results of the …

The BOUT++ transport code is run to study the effects of plasma drifts on the divertor out-in
asymmetries (DOIAs) of particle and heat fluxes and their decay widths for EAST lower …

The divertor operation in the detached plasma regime is necessary to reduce the loads on
the divertor plates in the ITER and DEMO tokamaks to acceptable values. The results of the …