2022年春の年会

講演情報

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VI. 核融合工学 » 601-2 核融合炉材料工学(炉材料,ブランケット,照射挙動)

[1L09-13] トリチウム増殖材,被覆技術

2022年3月16日(水) 14:45 〜 16:15 L会場

座長:小林 真 (核融合研)

15:30 〜 15:45

[1L12] Fabrication and characterization of zirconium oxide coating on tubular steel substrate by metal organic decomposition

*Khiem Duy Do1, Ryosuke Norizuki1, Hikaru Fujiwara1, Kento Shirota1, Teruya Tanaka2, Takumi Chikada1 (1. Shizuoka Univ., 2. NIFS)

キーワード:tritium, permeation, coating, corrosion, zirconium oxide, tube

Ceramic coatings in fusion reactor blankets have been investigated as multifunctional coatings for tritium permeation reduction, electrical insulation, and corrosion protection. Practically, the fabrication of homogeneous ceramic coatings on the fusion blanket components such as ducts and complex-shaped surfaces is challenging. In this work, we fabricated zirconium oxide coatings on 316L type stainless steel tubes of up to 250 mm in length by metal organic decomposition method. The prepared samples were characterized by surface and cross-sectional observations, deuterium permeation measurements, and electrical measurements. Corrosion tests by liquid lithium-lead exposure were also conducted to examine the compatibility of the coating.