Inspection of Arc Trails Formed in Stellarator/Heliotron Devices W7-X and LHD

被引:6
|
作者
Hwangbo, Dogyun [1 ,5 ]
Kajita, Shin [2 ]
Dhard, Chandra Prakash [3 ]
Tokitani, Masayuki [4 ]
Krause, Marco [3 ]
Naujoks, Dirk [3 ]
Masuzaki, Suguru [4 ]
Klose, Soeren [3 ]
Ohno, Noriyasu [1 ]
机构
[1] Nagoya Univ, Grad Sch Engn, Nagoya, Aichi 4648603, Japan
[2] Nagoya Univ, Inst Mat & Syst Sustainabil, Nagoya, Aichi 4648603, Japan
[3] Max Planck Inst Plasma Phys, Wendelsteinstr 1, D-17491 Greifswald, Germany
[4] Natl Inst Nat Sci, Natl Inst Fus Sci, Toki, Gifu 5095292, Japan
[5] Univ Tsukuba, Fac Pure & Appl Sci, Tsukuba, Ibaraki 3058577, Japan
来源
PLASMA AND FUSION RESEARCH | 2020年 / 15卷 / SpecialIssue1期
基金
日本学术振兴会;
关键词
Large Helical Device; Wendelstein; 7-X; plasma surface interaction; arcing; tungsten fuzz; PLASMA-FACING COMPONENTS; SURFACE FLASHOVER; EROSION;
D O I
10.1585/pfr.15.2402012
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Arc trails found in heliotron/stellarator devices Large Helical Device (LHD) and Wendelstein 7-X (W7-X) were inspected; arcing occurred on different locations at various situations. In LHD, a helium-plasma-induced tungsten nanostructure sample was installed and exposed to a LHD plasma. Many arc trails were formed only on the sample with nanostructures, suggesting an easy initiation of arcing compared to pristine tungsten. After the completion of annual campaign 2011 in LHD, arc trails appeared on a graphite divertor tile which was taken out for inspection. Because the arc trails had a linear shape, the arcing was likely caused by main discharge operation. In W7-X, some Langmuir-probes installed within the limiter tiles suffered severe damage with arc trails during the operational phase 1.1. After the operational phase 1.2b, in-vessel inspection was performed for the first time for all the plasma facing components focused on arcing. No arc trails appeared on graphite components including test divertor units. In turn, considerable number of the trails appeared on non-plasma exposed region. Most of the arc trails had no clear linearity, indicating that arcing initiated during glow discharge cleaning phase. Only a few trails seemed to be affected by the existence of an external magnetic field. A vast majority (80%) of arcs were initiated from the edge of surfaces, while half of arc trails starting on the interior region of surfaces were accompanied by deposition spots. Broad arc trails appeared on the surfaces of diagnostic ports and mirrors. (C) 2020 The Japan Society of Plasma Science and Nuclear Fusion Research
引用
收藏
页数:7
相关论文
共 50 条
  • [31] Protection of W7-X diagnostics from radiation heat loads
    Carls, Andre
    Koeppen, Matthias
    Fellinger, Joris
    Schauer, Felix
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 1433 - 1436
  • [32] Design and assembly technology for the thermal insulation of the W7-X cryostat
    Risse, K.
    Nagel, M.
    Pietsch, M.
    Braatz, A.
    Binni, A.
    Posselt, H.
    FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) : 720 - 723
  • [33] Assessment of carbon net erosion/deposition at the divertor of W7-X
    Mayer, M.
    Kandler, M.
    Dhard, C. P.
    Elgeti, S.
    Gao, Y.
    Jakubowski, M.
    Naujoks, D.
    Rudischhauser, L.
    NUCLEAR MATERIALS AND ENERGY, 2023, 34
  • [34] Optimisation of target plates for the W7-X divertor at stationary operation
    Boscary, J
    Greuner, H
    Hoffmann, FW
    Mendelevitch, B
    Pfefferle, K
    Renner, H
    FUSION ENGINEERING AND DESIGN, 2001, 56-57 : 279 - 283
  • [35] Asymmetry of W7-X magnet system introduced by torus assembly
    Fellinger, Joris
    Egorov, Konstantin
    Kallmeyer, Johannes Peter
    Bykov, Victor
    Schauer, Felix
    FUSION ENGINEERING AND DESIGN, 2014, 89 (9-10) : 2189 - 2193
  • [36] Structural analysis of W7-X:: Main results and critical issues
    Bykov, V.
    Schauer, F.
    Egorov, K.
    van Eeten, P.
    Damiani, C.
    D bner, A.
    Sochor, M.
    Sonnerup, L.
    Capriccioli, A.
    Tereshchenko, A.
    Jaksic, N.
    Daenner, W.
    Rumyancev, M.
    Zacharias, D.
    FUSION ENGINEERING AND DESIGN, 2007, 82 (5-14) : 1538 - 1548
  • [37] Thermal and mechanical analyses of W7-X plasma facing components for operation phase 2
    Wang, Zhongwei
    Boscary, Jean
    Schauer, Felix
    FUSION ENGINEERING AND DESIGN, 2020, 161
  • [38] Conceptual design of the next generation of W7-X divertor W-target elements
    Boscary, J.
    Ehrke, G.
    Frosi, P.
    Junghanns, P.
    Koncar, B.
    Mendelevitch, B.
    Naujoks, D.
    Neu, R.
    Richou, M.
    Selan, L.
    Tretter, J.
    Wang, Z.
    You, J. H.
    Zhang, K.
    FUSION ENGINEERING AND DESIGN, 2023, 192
  • [39] Design of endoscopes for monitoring water-cooled divertor in W7-X
    Fellinger, Joris
    Lippmann, Uwe
    Greve, Henry
    Alhashimi, Mohamad
    Schuelke, Mathias
    Akaslompolo, Simppa
    Drewelow, Peter
    Jakubowski, Marcin
    Koenig, Ralf
    Lorenz, Axel
    FUSION ENGINEERING AND DESIGN, 2020, 158
  • [40] Effect of error field correction coils on W7-X limiter loads
    Bozhenkov, S. A.
    Jakubowski, M. W.
    Niemann, H.
    Lazerson, S. A.
    Wurden, G. A.
    Biedermann, C.
    Kocsis, G.
    Koenig, R.
    Pisano, F.
    Stephey, L.
    Szepesi, T.
    Wenzel, U.
    Pedersen, T. S.
    Wolf, R. C.
    NUCLEAR FUSION, 2017, 57 (12)