TOWARD TUNGSTEN PLASMA-FACING COMPONENTS IN KSTAR: RESEARCH ON PLASMA-METAL WALL INTERACTION

0473219 - ÚFP 2017 RIV US eng J - Journal Article
Hong, S.-H. - Kim, K.M. - Song, J.-H. - Bang, E.-N. - Kim, H.-T. - Lee, K.-S. - Litnovsky, A. - Hellwig, M. - Seo, D.C. - Lee, H.H. - Kang, C.S. - Lee, H.-Y. - Hong, J.-H. - Bak, J.-G. - Kim, H.-S. - Juhn, J.-W. - Son, S.-H. - Kim, H.-K. - Douai, D. - Grisolia, C. - Wu, J. - Luo, G.-N. - Choe, W.-H. - Komm, Michael - van den Berg, M. - De Temmerman, G. - Pitts, R.
TOWARD TUNGSTEN PLASMA-FACING COMPONENTS IN KSTAR: RESEARCH ON PLASMA-METAL WALL INTERACTION.
Fusion Science and Technology. Roč. 68, č. 1 (2015), s. 36-43. ISSN 1536-1055. E-ISSN 1943-7641.
[International Conference on Open Magnetic Systems for Plasma Confinement (OS 2014)/10./. Daejeon, 26.08.2014-29.08.2014]
Institutional support: RVO:61389021
Keywords : Plasma-metal wall interaction * Tungsten technology
Subject RIV: BL - Plasma and Gas Discharge Physics
Impact factor: 0.799, year: 2015
http://dx.doi.org/10.13182/FST14-897

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.
Permanent Link: http://hdl.handle.net/11104/0270385