Plasma-wall interaction studies in W7-X: main results from the recent divertor operations

被引:13
作者
Dhard, C. P. [1 ]
Brezinsek, S. [2 ]
Mayer, M. [3 ]
Naujoks, D. [1 ]
Masuzaki, S. [4 ]
Zhao, D. [2 ]
Yi, R. [2 ]
Oelmann, J. [2 ]
Schmid, K. [3 ]
Romazanov, J. [2 ,5 ]
Pardanaud, C. [6 ]
Kandler, M. [3 ]
Kharwandikar, A. K. [1 ]
Schlisio, G. [1 ]
Volzke, O. [1 ]
Grote, H. [1 ]
Gao, Y. [1 ]
Rudischhauser, L. [1 ]
Goriaev, A. [7 ,8 ]
Wauters, T. [7 ]
Kirschner, A. [2 ]
Sereda, S. [2 ]
Wang, E. [2 ]
Rasinski, M. [2 ]
Dittmar, T. [2 ]
Motojima, G. [4 ]
Hwangbo, D. [9 ]
Kajita, S. [10 ]
Balden, M. [3 ]
Burwitz, V. V. [3 ]
Neu, R. [3 ,11 ]
Linsmeier, Ch [2 ]
机构
[1] Max Planck Inst Plasma Phys, Wendelsteinstr 1, D-17491 Greifswald, Germany
[2] Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, Partner Trilateral Euregio Cluster TEC, D-52425 Julich, Germany
[3] Max Plank Inst Plasmaphys, Boltzmannstr 2, D-85748 Garching, Germany
[4] Natl Inst Fus Sci, 322-6 Oroshi, Toki, Gifu 5095292, Japan
[5] Forschungszentrum Julich, Julich Supercomp Ctr, JARA HPC, D-52425 Julich, Germany
[6] Aix Marseille Univ, Lab PIIM, F-13013 Marseille, France
[7] LPP ERM KMS, Lab Plasma Phys, B-1000 Brussels, Belgium
[8] Univ Ghent, Dept Appl Phys, Ghent, Belgium
[9] Nagoya Univ, Grad Sch Engn, Dept Elect Engn, Chikusa Ku, Furo Cho, Nagoya, Aichi 4648603, Japan
[10] Nagoya Univ, Inst Mat & Syst Sustainabil, Chikusa Ku, Furo Cho, Nagoya, Aichi 4648603, Japan
[11] Tech Univ Munich, Boltzmannstr 15, D-85748 Garching, Germany
关键词
wendelstein; 7-X; plasma-facing components; plasma-wall interaction; erosion and deposition; graphite; CHEMICAL EROSION; 1ST WALL; DEPOSITION; COMPONENTS; HYDROGEN;
D O I
10.1088/1402-4896/ac35c0
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
Wendelstein 7-X (W7-X) is an optimized stellarator with a 3-dimensional five-fold modular geometry. The plasma-wall-interaction (PWI) investigations in the complex 3D geometry of W7-X were carried out by in situ spectroscopic observations, exhaust gas analysis and post-mortem measurements on a large number of plasma-facing components extracted after campaigns. The investigations showed that the divertor strike line areas on the divertor targets appeared to be the major source of carbon impurities. After multistep erosion and deposition events, carbon was found to be deposited largely at the first wall components, with thick deposits of >1 mu m on some baffle tiles, moderate deposits on toroidal closure tiles and thin deposits at the heat shield tiles and the outer wall panels. Some amount of the eroded carbon was pumped out via the vacuum pumps as volatile hydrocarbons and carbon oxides (CO, CO2) formed due to the chemical processes. Boron was introduced by three boronizations and one boron powder injection experiment. Thin boron-dominated layers were found on the inner heat shield and the outer wall panels, some boron was also found at the test divertor unit and in redeposited layers together with carbon. Local erosion/deposition and global migration processes were studied using field-line transport simulations, analytical estimations, 3D-WallDYN and ERO2.0 modeling in standard magnetic field configuration.
引用
收藏
页数:15
相关论文
共 49 条
  • [1] Analysis of mixed-material layers deposited on the toroidal array probes during the FY 2012 LHD plasma campaign
    Alimov, V. Kh
    Yajima, M.
    Masuzaki, S.
    Tokitani, M.
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 147
  • [2] Collection strategy, inner morphology, and size distribution of dust particles in ASDEX Upgrade
    Balden, M.
    Endstrasser, N.
    Humrickhouse, P. W.
    Rohde, V.
    Rasinski, M.
    von Toussaint, U.
    Elgeti, S.
    Neu, R.
    [J]. NUCLEAR FUSION, 2014, 54 (07)
  • [3] Service oriented architecture for scientific analysis at W7-X. An example of a field line tracer
    Bozhenkov, S. A.
    Geiger, J.
    Grahl, M.
    Kisslinger, J.
    Werner, A.
    Wolf, R. C.
    [J]. FUSION ENGINEERING AND DESIGN, 2013, 88 (11) : 2997 - 3006
  • [4] Brakel R., 2021, COMMUNICATION
  • [5] Plasma-surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components
    Brezinsek, S.
    Dhard, C. P.
    Jakubowski, M.
    Koenig, R.
    Masuzaki, S.
    Mayer, M.
    Naujoks, D.
    Romazanov, J.
    Schmid, K.
    Schmitz, O.
    Zhao, D.
    Balden, M.
    Brakel, R.
    Butterschoen, B.
    Dittmar, T.
    Drews, P.
    Effenberg, F.
    Elgeti, S.
    Ford, O.
    Fortuna-Zalesna, E.
    Fuchert, G.
    Gao, Y.
    Goriaev, A.
    Hakola, A.
    Kremeyer, T.
    Krychowiak, M.
    Liang, Y.
    Linsmeier, Ch
    Lunsford, R.
    Motojima, G.
    Neu, R.
    Neubauer, O.
    Oelmann, J.
    Petersson, P.
    Rasinski, M.
    Rubel, M.
    Sereda, S.
    Sergienko, G.
    Pedersen, T. Sunn
    Vuoriheimo, T.
    Wang, E.
    Wauters, T.
    Winters, V
    Zhao, M.
    Yi, R.
    [J]. NUCLEAR FUSION, 2022, 62 (01)
  • [7] Material migration and fuel retention studies during the JET carbon divertor campaigns
    Coad, J. P.
    Rubel, M.
    Likonen, J.
    Bekris, N.
    Brezinsek, S.
    Matthew, G. F.
    Mayer, M.
    Widdowson, A. M.
    Abduallev, S.
    Abhangi, M.
    Abreu, P.
    Afzal, M.
    Aggarwal, K. M.
    Ahlgren, T.
    Ahn, J. H.
    Aho-Mantila, L.
    Aiba, N.
    Airila, M.
    Albanese, R.
    Aldred, V.
    Alegre, D.
    Alessi, E.
    Aleynikov, P.
    Alfier, A.
    Alkseev, A.
    Allinson, M.
    Alper, B.
    Alves, E.
    Ambrosino, G.
    Ambrosino, R.
    Amicucci, L.
    Amosov, V.
    Sunden, E. Andersson
    Angelone, M.
    Anghel, M.
    Angioni, C.
    Appel, L.
    Appelbee, C.
    Arena, P.
    Ariola, M.
    Arnichand, H.
    Arshad, S.
    Ash, A.
    Ashikawa, N.
    Aslanyan, V.
    Asunta, O.
    Auriemma, F.
    Austin, Y.
    Avotina, L.
    Axton, M. D.
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 138 : 78 - 108
  • [8] Inspection of W 7-X plasma-facing components after the operation phase OP1.2b: observations and first assessments
    Dhard, C. P.
    Aekaeslompolo, S.
    Balden, M.
    Baldzuhn, J.
    Biedermann, C.
    Braeuer, T.
    Brezinsek, S.
    Endler, M.
    Hayashi, Y.
    Hwangbo, D.
    Kajita, S.
    Krause, M.
    Kornejew, P.
    Masuzaki, S.
    Mayer, M.
    Motojima, G.
    Naujoks, D.
    Otte, M.
    Rohde, V.
    [J]. PHYSICA SCRIPTA, 2020, T171 (01)
  • [9] Preparation of erosion and deposition investigations on plasma facing components in Wendelstein 7-X
    Dhard, C. P.
    Balden, M.
    Braeuer, T.
    Brezinsek, S.
    Coenen, J. W.
    Dudek, A.
    Ehrke, G.
    Hathiramani, D.
    Klose, S.
    Koenig, R.
    Laux, M.
    Linsmeier, Ch
    Manhard, A.
    Masuzaki, S.
    Mayer, M.
    Motojima, G.
    Naujoks, D.
    Neu, R.
    Neubauer, O.
    Rack, M.
    Ruset, C.
    Schwarz-Selinger, T.
    Pedersen, T. Sunn
    Tokitani, M.
    Unterberg, B.
    Yajima, M.
    [J]. PHYSICA SCRIPTA, 2017, T170
  • [10] Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration
    Dhard, Chandra Prakash
    Mayer, Matej
    Brezinsek, Sebastijan
    Masuzaki, Suguru
    Motojima, Gen
    Koenig, Ralf
    Pedersen, Thomas Sunn
    Neu, Rudolf
    Hathiramani, Dag
    Krause, Marco
    Ehrke, Gunnar
    Ruset, Cristian
    Schwarz-Selinger, Thomas
    Balden, Martin
    Burwitz, Vassily Vadimovitch
    Coenen, Jan Willem
    Linsmeier, Christian
    Naujoks, Dirk
    Neubauer, Olaf
    Rack, Michael
    Tokitani, Masayuki
    Oelmann, Jannis
    Li, Cong
    Rasinski, Marcin
    Hoeschen, Daniel
    Yajima, Miyuki
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 146 : 242 - 245