2022 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1L09-13] Tritium Breeder and Coating Technique

Wed. Mar 16, 2022 2:45 PM - 4:15 PM Room L

Chair: Makoto Kobayashi (NIFS)

3:30 PM - 3:45 PM

[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)

Keywords: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.