10:55 〜 11:10
[3A06] The effect of applied tensile stress on microstructure evolution under high dose ion irradiation in Zry-2
キーワード：Zirconium alloy, Applied stress, Ion irradiation, Irradiation effects, Energy-dispersive spectroscopy
Zircaloy-2 is located closest to the fuel as the fuel cladding tube in BWRs. During reactor operation, fuel cladding tubes experience stress due to UO2 pellet-cladding interactions. In this study, we investigated the microstructural evolution of Zircaloy-2 under 3.2 MeV Ni3+ ion irradiation using TEM examination and EDS analysis. The materials were irradiated at 300 °C and 400 °C under applied stress. At high-dose irradiation levels, loops only nucleated above a threshold dose of 20 dpa at 400 °C. The dissolution of Fe atoms from Zr(Fe, Cr)2 precipitates due to irradiation was detected using EDS. However, the effect of stress on the dissolution rate of Fe-rich precipitates was minor.
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