Damage and deuterium retention of re-solidified tungsten following vertical displacement event-like heat load

Y. Hamaji, H. T. Lee, A. Kreter, S. Möller, M. Rasinski, M. Tokitani, S. Masuzaki, A. Sagara, M. Oya, K. Ibano, Y. Ueda, R. Sakamoto

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Surface morphology and hydrogen isotope retention of W specimen melted with vertical displacement event-like heat load and subsequent deuterium (D) plasma exposure were studied. Applied heat loads using electron beam without raster scanning were about 190 and 230 MW/m2 in heat flux and 0.08, 0.12 and 0.16 s in duration. After the heat load application, specimens showed apparent melting spots with grain growth or dense micrometer scale convex structure. Cracks were observed only in the part with the convex structure. D retention in the melted part of specimens was not significantly larger than in the reference specimen despite large changes of surface characteristics.

元の言語英語
ページ(範囲)1303-1307
ページ数5
ジャーナルNuclear Materials and Energy
12
DOI
出版物ステータス出版済み - 8 2017

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science (miscellaneous)
  • Nuclear Energy and Engineering

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    Hamaji, Y., Lee, H. T., Kreter, A., Möller, S., Rasinski, M., Tokitani, M., Masuzaki, S., Sagara, A., Oya, M., Ibano, K., Ueda, Y., & Sakamoto, R. (2017). Damage and deuterium retention of re-solidified tungsten following vertical displacement event-like heat load. Nuclear Materials and Energy, 12, 1303-1307. https://doi.org/10.1016/j.nme.2016.11.003