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@ARTICLE{Xu:850920,
author = {Xu, S. and Rack, M. and Liang, Yunfeng and Huang, J. and
Jia, M. and Feng, Y. and Cosfeld, J. and Zhang, H. and Liu,
S. and Gao, Yu and Gan, K. and Feng, W. and Wang, L. and
Zholobenko, W. and Reiter, D.},
title = {{F}irst three-dimensional edge plasma transport simulations
with magnetic perturbations induced by lower hybrid waves on
{EAST}},
journal = {Nuclear fusion},
volume = {58},
number = {10},
issn = {1741-4326},
address = {Vienna},
publisher = {IAEA},
reportid = {FZJ-2018-04654},
pages = {106008 -},
year = {2018},
abstract = {Recent experiments from the Experimental Advanced
Superconducting Tokamak (EAST) show that lower hybrid waves
(LHWs) can profoundly change the magnetic topology by
inducing helical current filaments flowing along magnetic
field lines in the scrape-off layer. Here, it is
investigated for the first time how these magnetic
perturbations caused by LHWs affect the edge plasma
transport utilizing the three-dimensional Monte Carlo code
EMC3-EIRENE, both in double-null and single-null
configurations. The 3D magnetic topology structure is
reflected in the plasma properties, due to much stronger
parallel field transport compared with cross field
diffusion. Good qualitative agreements between simulation
results and experimental data from various edge diagnostics
demonstrate that the EMC3-EIRENE code now is capable of
taking into account the LHW-induced magnetic perturbation
fields with both physical and geometrical effects being
considered. Combined with experimental observations, the
simulation results strongly support that total current
amplitude of LHW-induced filaments increases with an
increase in LHW input power. It can further deepen the
penetration depth of the additional transport channel by
extending the stochastic edge layer, and influence the ratio
of heat (or particle) flux between split striated and
original strike line on divertor targets. The 3D simulation
results also indicate that the additional plasma transport
channel induced by LHWs can significantly cause the
redistribution of heat load between inner and outer divertor
targets, which could not be found by the field line tracing
method in previous works.},
cin = {IEK-4 / JARA-HPC},
ddc = {530},
cid = {I:(DE-Juel1)IEK-4-20101013 / $I:(DE-82)080012_20140620$},
pnm = {174 - Plasma-Wall-Interaction (POF3-174) / Predictive
EMC3-EIRENE modelling and diagnostic interpretation for
Wendelstein 7-X and EAST $(jiek42_20180501)$},
pid = {G:(DE-HGF)POF3-174 / $G:(DE-Juel1)jiek42_20180501$},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000440052000001},
doi = {10.1088/1741-4326/aad296},
url = {https://juser.fz-juelich.de/record/850920},
}