Erosion and redeposition pattern on the W7-X graphite test divertor unit tile

被引：0

作者：

Fortuna-Zalesna, Elzbieta ^{[1
]}

Zielinski, Witold ^{[1
]}

Ciupinski, Lukasz ^{[1
]}

Spychalski, Maciej ^{[1
]}

Dhard, Chandra Prakash ^{[2
]}

Naujoks, Dirk ^{[2
]}

Rasinski, Marcin ^{[3
]}

Brezinsek, Sebastijan ^{[3
]}

机构：

[1] Warsaw Univ Technol, Fac Mat Sci & Engn, Woloska 141, PL-02507 Warsaw, Poland

[2] Max Planck Inst Plasma Phys, D-17491 Greifswald, Germany

[3] Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, Partner Trilateral Euregio Cluster TEC, D-52425 Julich, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2023年 / 191卷

关键词：

Wendelstein; 7-X; Plasma-facing components; Plasma-wall interaction; Erosion and deposition; Graphite; ANGULAR-DEPENDENCE; SURFACE-ROUGHNESS; SPUTTER YIELD; DEVICES;

D O I：

10.1016/j.fusengdes.2023.113589

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：

A set of plasma-facing components was retrieved from the W7-X vessel after OP1.2b campaign with an inertially cooled Test Divertor Unit (TDU) and analyzed postmortem to provide data on the plasma-surface interactions processes in the complex device geometry. In the present study, the lower TDU horizontal target (HT) graphite tile HM19TM400hTE2 exposed to the plasma during both OP 1.2 campaigns was examined. The surface modification of the material caused by the plasma-wall interactions was determined. The study employed several microscopy methods including SEM, FIB, STEM, TEM, EDX, and optical profilometry which showed that (i) distinct erosion zone was located at the inner HT strike line position, (ii) the area covered by a pronounced deposit was located adjacent the erosion zone, (iii) the target finger substructures positioned close to the outboard side was unaltered, and (iv) significant changes to surface roughness values along the length of the plate occurred.

引用

页数：8

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