Baseline high heat flux and plasma facing materials for fusion

Y. Ueda, K. Schmid, M. Balden, J. W. Coenen, Th Loewenhoff, A. Ito, A. Hasegawa, C. Hardie, M. Porton, M. Gilbert

研究成果: Article査読

122 被引用数 (Scopus)

抄録

In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).

本文言語English
論文番号092006
ジャーナルNuclear Fusion
57
9
DOI
出版ステータスPublished - 2017 6月 9

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 凝縮系物理学

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