Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma

Y. Ueda, M. Oya, Y. Hamaji, H. T. Lee, H. Kurishita, Y. Torikai, N. Yoshida, A. Kreter, J. W. Coenen, A. Litnovsky, V. Philipps

研究成果: ジャーナルへの寄稿会議記事査読

11 被引用数 (Scopus)

抄録

In order to evaluate the applicability of toughened, fine-grained, recrystallized (TFGR)-W to tokamak edge plasma environment, two TFGR-W specimens (TFGR-W 1.1wt%TiC and TFGR-W 3.3wt%TaC) were exposed to 31 identical ohmic discharges in the TEXTOR tokamak by means of a limiter lock system. The highest surface temperature reached was about 1300 °C. Under these temperature conditions, the bulk microstructure and dispersoids distribution of both TFGR-W remained intact, suggesting that these TFGR-W tungsten materials have sufficient stability under these plasma loading conditions. The erosion of TiC dispersoids on the surface was enhanced by plasma exposure above 1150 °C, while such enhanced erosion was not observed for TaC dispersoids probably due to the higher melting temperature of Ta than Ti.

本文言語英語
論文番号014038
ジャーナルPhysica Scripta
T159
DOI
出版ステータス出版済み - 2014
外部発表はい
イベント14th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2013 - Julich, ドイツ
継続期間: 5月 13 20135月 17 2013

!!!All Science Journal Classification (ASJC) codes

  • 原子分子物理学および光学
  • 数理物理学
  • 凝縮系物理学

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