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| 001 | 891338 | ||
| 005 | 20240708133240.0 | ||
| 037 | _ | _ | |a FZJ-2021-01431 |
| 100 | 1 | _ | |a Park, Heesung |0 P:(DE-Juel1)179078 |b 0 |
| 111 | 2 | _ | |a 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 2020) |c virtuell |d 2021-01-25 - 2021-01-29 |w virtuell |
| 245 | _ | _ | |a Study of Erosion of Carbon and Tungsten Divertor in KSTAR using ERO code |
| 260 | _ | _ | |c 2021 |
| 336 | 7 | _ | |a Abstract |b abstract |m abstract |0 PUB:(DE-HGF)1 |s 1616489245_1915 |2 PUB:(DE-HGF) |
| 336 | 7 | _ | |a Conference Paper |0 33 |2 EndNote |
| 336 | 7 | _ | |a INPROCEEDINGS |2 BibTeX |
| 336 | 7 | _ | |a conferenceObject |2 DRIVER |
| 336 | 7 | _ | |a Output Types/Conference Abstract |2 DataCite |
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| 520 | _ | _ | |a 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. |
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| 700 | 1 | _ | |a Ra, Ookjoo |0 P:(DE-HGF)0 |b 1 |
| 700 | 1 | _ | |a Kwon, Kyu Been |0 P:(DE-Juel1)179077 |b 2 |
| 700 | 1 | _ | |a Hong, Suk-Ho |0 P:(DE-Juel1)164150 |b 3 |u fzj |
| 700 | 1 | _ | |a Lee, Hyungho |0 P:(DE-HGF)0 |b 4 |
| 700 | 1 | _ | |a Kim, Kyungmin |0 P:(DE-HGF)0 |b 5 |
| 700 | 1 | _ | |a Kim, Kyungmin |0 P:(DE-HGF)0 |b 6 |
| 700 | 1 | _ | |a Son, Soohyun |0 P:(DE-HGF)0 |b 7 |
| 700 | 1 | _ | |a Romanov, J. |0 P:(DE-HGF)0 |b 8 |
| 700 | 1 | _ | |a Eksaeva, Alina |0 P:(DE-Juel1)171509 |b 9 |e Corresponding author |u fzj |
| 700 | 1 | _ | |a Kirschner, A. |0 P:(DE-Juel1)2620 |b 10 |u fzj |
| 700 | 1 | _ | |a Lee, Hae June |0 P:(DE-HGF)0 |b 11 |
| 700 | 1 | _ | |a Hur, Min Sup |0 P:(DE-HGF)0 |b 12 |
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