核融合炉工学入門　ＩＩ　　ＩＩ‐１核融合炉材料工学　　炉内材料

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書誌事項

タイトル別名
  • Material technologies for fusion reactor. In-vessel materials.
  • カク ユウゴウロ ザイリョウ コウガク ロナイ ザイリョウ
  • In-Vessel Materials
  • 炉内材料

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抄録

Chemical sputtering and radiation-enhanced sublimation of graphite have been the subject of many intense researches. Chemical form of desorbing species and synergism between thermal atoms and energetic atoms are among the controversial problems of surface erosion of graphite. Self-sustaining surface segregated low-Z layers have been proposed as a new approach to impurity control. Hydrogen isotope dynamics between plasma and first wall is very important in controlling the plasma, and hence the fusion reactor itself. In this sense, surface recombination coefficient of hydrogen must be evaluated for various materials with various surface conditions. Its theory and surface impurity effect are described.

収録刊行物

  • 核融合研究

    核融合研究 56 (2), 96-104, 1986

    社団法人 プラズマ・核融合学会

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