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Report No.
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R&D of advanced stainless steels for BWR fuel claddings, 3-7; Evaluation of irradiation behavior

Hashimoto, Naoyuki*; Toyoda, Kodai*; Tang, Y.*; Sakamoto, Kan*; Yamashita, Shinichiro   

To investigate irradiation stability of FeCrAl-ODS stainless steel (Fe-12Cr-6Al-0.5Ti-0.4Zr -0.24Ex.O-0.5Y$$_{2}$$O$$_{3}$$), the ion irradiation was carried out recrystallized and extruded materials. The recrystallized and extruded materials were irradiated at TIARA of Quantum and Radiological Science and Technology (Takasaki) and DuET of Kyoto University, respectively. The irradiated sample was thinned by FIB and microstructure observation was performed using 200 keV transmission electron microscopy. To grasp formation and grown-up behavior of cavity under irradiation, the migration energy in cavity was experimentally drawn out the irradiation experiment. Energy by the density functional theory was calculated in consideration of the interaction between vacancy and Al atom.

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