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TOWARD TUNGSTEN PLASMA-FACING COMPONENTS IN KSTAR: RESEARCH ON PLASMA-METAL WALL INTERACTION
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SYSNO ASEP 0473219 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title TOWARD TUNGSTEN PLASMA-FACING COMPONENTS IN KSTAR: RESEARCH ON PLASMA-METAL WALL INTERACTION Author(s) Hong, S.-H. (KR)
Kim, K.M. (KR)
Song, J.-H. (KR)
Bang, E.-N. (KR)
Kim, H.-T. (KR)
Lee, K.-S. (KR)
Litnovsky, A. (DE)
Hellwig, M. (DE)
Seo, D.C. (KR)
Lee, H.H. (KR)
Kang, C.S. (KR)
Lee, H.-Y. (KR)
Hong, J.-H. (KR)
Bak, J.-G. (KR)
Kim, H.-S. (KR)
Juhn, J.-W. (KR)
Son, S.-H. (KR)
Kim, H.-K. (KR)
Douai, D. (FR)
Grisolia, C. (FR)
Wu, J. (CN)
Luo, G.-N. (CN)
Choe, W.-H. (KR)
Komm, Michael (UFP-V) RID, ORCID
van den Berg, M. (NL)
De Temmerman, G. (FR)
Pitts, R. (FR)Source Title Fusion Science and Technology. - : Taylor & Francis - ISSN 1536-1055
Roč. 68, č. 1 (2015), s. 36-43Number of pages 8 s. Publication form Print - P Action International Conference on Open Magnetic Systems for Plasma Confinement (OS 2014)/10./ Event date 26.08.2014 - 29.08.2014 VEvent location Daejeon Country KR - Korea, Republic of Event type WRD Language eng - English Country US - United States Keywords Plasma-metal wall interaction ; Tungsten technology Subject RIV BL - Plasma and Gas Discharge Physics Institutional support UFP-V - RVO:61389021 UT WOS 000358104600007 EID SCOPUS 84940495832 DOI 10.13182/FST14-897 Annotation One of the main missions of KSTAR is to develop long pulse operation capability relevant to the production of fusion energy. After a full metal wall configuration was decided for ITER, a major upgrade for KSTAR was planned, to a tungsten first wall similar to the JET ITER-like wall (coatings and bulk tungsten plasma-facing components). To accomplish the upgrade, tungsten bonding technology has been developed and tested. Since the leading edges of each castellation structure have to be protected, shaping of tungsten blocks has been studied by ANSYS simulation, and the miniaturized castellation has been exposed to Ohmic plasma to confirm the simulation results. It is found that a shaped castellation block has more heat handling capability than a conventional block. For more dedicated experiments, a multipurpose castellation block is fabricated and exposed to Ohmic, L- and H-mode plasmas and observed by IR camera from the top. During the fabrication and assembly of the blocks, leading edges due to engineering limits with a maximum level up to 0.5 mm have been observed, and these have to be minimized for the future fusion machine. Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2017
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