CHARACTERIZATION OF SURFACE MODIFICATIONS OF PLASMA-FACING COMPONENTS IN LHD

被引:15
|
作者
Tokitani, M. [1 ]
Yoshida, N. [2 ]
Miyamoto, M. [3 ]
Hino, T. [4 ]
Nobuta, Y. [4 ]
Masuzaki, S. [1 ]
Ashikawa, N. [1 ]
Sagara, A. [1 ]
Noda, N. [1 ]
Yamada, H. [1 ]
Komori, A. [1 ]
机构
[1] Natl Inst Nat Sci, Natl Inst Fus Sci, Toki, Gifu 5095292, Japan
[2] Kyushu Univ, Appl Mech Res Inst, Fukuoka 8168580, Japan
[3] Shimane Univ, Dept Mat Sci, Matsue, Shimane 6908504, Japan
[4] Hokkaido Univ, Lab Plasma Phys & Engn, Sapporo, Hokkaido 0608628, Japan
关键词
LHD; plasma-wall interaction; radiation effects; particle retention; LARGE HELICAL DEVICE; MATERIAL PROBE ANALYSIS; RETENTION PROPERTIES; DIVERTOR OPERATION; ION IRRADIATION; BORONIZED WALL; TUNGSTEN; HELIUM; ENERGY; DESORPTION;
D O I
10.13182/FST10-A10817
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The Large Helical Device (LHD) has been equipped with movable- and fixed-type material probe systems. Characterization studies of surface modifications on plasma-facing components (PFCs) have been actively progressing by using these probes. After exposure of the PFCs to the plasma, various kinds of surface analysis were conducted. The first walls and divertor tiles of LHD are made of stainless steel and isotropic graphite (IG-430U, Toyo Tanso Co., Ltd.), respectively. They are frequently exposed not only to high-power pulsed main discharges but also to wall-conditioning processes such as glow discharge cleaning (GDC). Thus, the surfaces of the PFCs are drastically changed due to sputtering erosion, impurity deposition, and melting damage. Graphite divertor tiles are eroded primarily during the main discharges; the eroded carbon migrates and deposits on the first-wall surfaces, particularly near the divertor array. First walls are eroded mainly during GDC, which significantly changes the condition of the PFCs. During the main discharges, the majority of incidence particles to the first wall are energetic neutrals (CX neutrals) generated by charge-exchange collisions. Studies of the material damage caused by CX neutrals also have been done. In this paper, the characteristics of surface modifications of PFCs by means of material probe experiments and subsequent surface analysis are summarized.
引用
收藏
页码:305 / 320
页数:16
相关论文
共 50 条
  • [31] Qualification of tungsten coatings on plasma-facing components for JET
    Maier, H.
    Neu, R.
    Greuner, H.
    Boeswirth, B.
    Balden, M.
    Lindig, S.
    Matthews, G. F.
    Rasinski, M.
    Wienhold, P.
    Wiltner, A.
    PHYSICA SCRIPTA, 2009, T138
  • [32] Progress in the Realization of μ-Brush W for Plasma-Facing Components
    Dorow-Gerspach, Daniel
    Derra, Thomas
    Gipperich, Marius
    Loewenhoff, Thorsten
    Pintsuk, Gerald
    Terra, Alexis
    Weber, Thomas
    Wirtz, Marius
    Linsmeier, Christian
    JOURNAL OF NUCLEAR ENGINEERING, 2022, 3 (04): : 333 - 341
  • [33] PROPERTIES AND PERFORMANCE OF BERYLLIUM AND CARBON FOR PLASMA-FACING COMPONENTS
    DIETZ, KJ
    FUSION TECHNOLOGY, 1991, 19 (04): : 2031 - 2034
  • [34] Physics basis and design of the ITER plasma-facing components
    Pitts, R. A.
    Carpentier, S.
    Escourbiac, F.
    Hirai, T.
    Komarov, V.
    Kukushkin, A. S.
    Lisgo, S.
    Loarte, A.
    Merola, M.
    Mitteau, R.
    Raffray, A. R.
    Shimada, M.
    Stangeby, P. C.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) : S957 - S964
  • [35] Fusion tritons and plasma-facing components in a fusion reactor
    Kurki-Suonio, T.
    Hynonen, V.
    Ahlgren, T.
    Nordlund, K.
    Sugiyama, K.
    Dux, R.
    EPL, 2007, 78 (06)
  • [36] Tritium inventory in the materials of the ITER plasma-facing components
    Federici, G
    Skinner, CH
    NUCLEAR FUSION RESEARCH: UNDERSTANDING PLASMA-SURFACE INTERACTIONS, 2005, 78 : 287 - 317
  • [37] DEVELOPMENT OF PLASMA-FACING COMPONENTS WITH FUNCTIONALLY GRADIENT LAYERS
    MORIMOTO, M
    KUDOUGH, F
    ONOZUKA, M
    TSUNODA, H
    TOYODA, M
    FUSION TECHNOLOGY, 1994, 26 (03): : 503 - 506
  • [38] A review of the LIBS analysis for the plasma-facing components diagnostics
    Maurya, Gulab Singh
    Marin-Roldan, Alicia
    Veis, Pavel
    Pathak, Ashok Kumar
    Sen, Pratik
    JOURNAL OF NUCLEAR MATERIALS, 2020, 541 (541)
  • [39] Effect of ELMS and disruptions on FNSF plasma-facing components
    Blanchard, James
    Martin, Carl
    Liu, Wei
    FUSION ENGINEERING AND DESIGN, 2018, 135 : 337 - 345
  • [40] Tungsten as material for plasma-facing components in fusion devices
    Philipps, V.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) : S2 - S9