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

被引：15

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

来源：

PHYSICA SCRIPTA | 2021年 / 96卷 / 12期

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

页数：15

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