Tokyo Institute of Technology · Materials Science
Professor Masatoshi Kondo's research lab specializes in advanced materials science for advanced nuclear energy systems, with a primary focus on corrosion resistance and material stability in liquid metal coolants such as lead-bismuth eutectic (LBE) and lithium lead (LiPb), as well as molten salts like Flibe. The lab investigates protective oxide layer formation, including α-Al₂O₃ and spinel-type γ-LiAlO₂, on advanced alloys such as ODS FeCrAl and Ni-based superalloys under extreme conditions relevant to fast breeder and fusion reactors. Their work combines thermodynamic analysis, static and flowing corrosion tests, and advanced characterization techniques like STEM/EELS to understand material degradation mechanisms and improve the longevity and safety of reactor components.
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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