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@INPROCEEDINGS{Park:891338,
author = {Park, Heesung and Ra, Ookjoo and Kwon, Kyu Been and Hong,
Suk-Ho and Lee, Hyungho and Kim, Kyungmin and Kim, Kyungmin
and Son, Soohyun and Romanov, J. and Eksaeva, Alina and
Kirschner, A. and Lee, Hae June and Hur, Min Sup},
title = {{S}tudy of {E}rosion of {C}arbon and {T}ungsten {D}ivertor
in {KSTAR} using {ERO} code},
reportid = {FZJ-2021-01431},
year = {2021},
abstract = {Study of Erosion of Carbon and Tungsten Divertor in KSTAR
using ERO codeHeesung Parka,1, Ookjoo Rab, Kyu Been Kwonb,
Suk-Ho Hongc, Hyungho Leec,Kyungmin Kimc, Kyungmin Kimc,
Soohyun Son c, J. Romanovd, A. Eksaevad, A. Kirschnerd, Hae
June Lee a, Min Sup Hurb,†National Fusion Research
Institute, 169-148 Gwahak-ro, Yuseong-gu, Daejeon 34133,
Koreaa Department of Electrical Computer Engineering, Pusan
National University, 2 Busandaehak-ro 63beon-gil,
Geumjeong-gu, Busan 46241, Koreab Department of Physics,
UNIST, 50 UNIST-gil, Eonyang-eup, Ulju-gun, Ulsan 44919,
Koreac National Fusion Research Institute, 169-148
Gwahak-ro, Yuseong-gu, Daejeon 34133, Koread
Forschungszentrum Julich GmbH, Institut fur Energie- und
Klimaforschung – Plasmaphysik, Partner of the Trilateral
Euregio Cluster (TEC), Julich 52425, Germany
phs@pusan.ac.kr†Corresponding to
mshur@unist.ac.krImpurities caused by sputtering of divertor
targets and walls differ depending on the surface
components: Low Z materials have benefits of radiation
control and low core penetration, but, they have very high
erosion rate. On the other hand, high Z materials have low
erosion rate, while they show high core contamination [1].
KSTAR is a full carbon machine, in which 3400 blocks of
graphite tiles were installed. Although carbon transport and
migration were intensively studied in the past, the carbon
transport in KSTAR was never studied systematically.
Furthermore, KSTAR is on the way towards full tungsten wall:
The erosion of new tungsten divertor and the transport of
eroded tungsten atoms has to be studied. The 3D ERO code is
a tool that can simulate impurity transport and wall
interaction using SOLPS data as background plasma conditions
in magnetically confined fusion relevant devices [2]. In
this study, the erosion has been simulated for the surfaces
of PFCs in KSTAR, made of carbon and tungsten using the ERO
code with an EFIT equilibrium data from a shot #21376. We
demonstrate changes in the characteristics of the erosion
rates and concentrated erosion positions on the surface when
the surface material switches from the carbon to the
tungsten in the KSTAR. We discuss the limitations of each
material for the long-pulse operation.[1] S.Brezinsek et
al., Nucl. Fusion 54 (2014) 103001.},
month = {Jan},
date = {2021-01-25},
organization = {24th International Conference on
Plasma Surface Interactions in
Controlled Fusion Devices (PSI 2020),
virtuell (virtuell), 25 Jan 2021 - 29
Jan 2021},
cin = {IEK-4},
cid = {I:(DE-Juel1)IEK-4-20101013},
pnm = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
pid = {G:(DE-HGF)POF4-134},
typ = {PUB:(DE-HGF)1},
url = {https://juser.fz-juelich.de/record/891338},
}