東京工業大学 · 材料科学
本研究室では、高速炉や核融合炉に応用される液体金属冷却材（Pb-Bi、LiPb、Flibeなど）における材料の腐食挙動と耐久性を、実験的・金属組織的・熱力学的アプローチを融合して解明しています。特に、酸化被覆層の形成機構や、液体金属中での材料の長時間安定性を評価する腐食試験を基盤として、核融合・原子力炉の構造材料の開発に貢献しています。
Figures are computed from collected data and may differ slightly.
For the development of lead-bismuth (Pb-Bi) cooled fast breeder reactors, the corrosion characteristics of various steels in a flowing Pb-Bi were investigated by means of steel corrosion test performed in the flowing Pb-Bi for 1,000 h. It was found that liquid metal corrosion was inhibited by single or multiple oxide layers formed on the steel surfaces. The oxide layers can be classified to an inner layer and an outer one. The existence of the inner oxide layer might be more important for the co
Molten salt LiF-BeF2 (Flibe) is one of candidates for self-cooled tritium breeder in fusion blanket system. The Ni based alloys of Hastelloy C-276 (6.28Fe, 15.67Cr, 0.42Mn, 15.83Mo, 3.34W, Ni as balance), Inconel 600(7.02Fe, 15.75Cr, Ni as balance) and Inconel 625 (4.12Fe, 21.94Cr, 9.10Mo, Ni as balance) are candidates of structural material of blanket loop components at down stream. Corrosion characteristics of these alloys were investigated by corrosion test in static Flibe at 500°C and 600°C
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