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Liu, P.*; Du, Y.*; Yoshida, Kenta*; Kitagaki, Toru; Ikeda, Atsushi; Shimada, Yusuke*; Nagai, Yasuyoshi*
no journal, ,
Sato, Yuki*; Abe, Yosuke; Okubo, Kenji*; Tanioka, Takashi*
no journal, ,
Self-interstitial atom (SIA) clusters are produced from collision cascades, after which they escape quickly through one-dimensional (1D) migration, affecting the microstructural evolution in materials. In this study, we examined effects of a specimen purity and heat treatment for specimen preparation on the 1D migration behavior in copper by in situ observations using a high-voltage electron microscopy. The results showed that for high-purity specimens, 1D migration distances were considerably suppressed by a standard heat treatment (cold-rolled, punched-out, and annealed) compared to those without annealing, while almost unchanged by the bulk heat treatment (annealed, mechanically polished, and punched-out). For low-purity specimens, 1D migration distances were not largely changed even by the standard heat treatment. Regarding to specimens with the standard heat treatment, 1D migration distances were about the same, irrespective to the specimen purity. These results suggest that not only residual impurities but also impurities induced by the heat treatment affect the 1D migration behavior.
Nakabachi, Kaito*; Yokoyama, Kenichi*; Ishijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi
no journal, ,
The effects of thermal aging on hydrogen embrittlement behavior were investigated for Zr/Ta/SUS explosive joints used in spent nuclear fuel reprocessing plants, especially at the Zr/Ta interface, which is considered to be susceptible to hydrogen embrittlement. The results showed that brittle fracture occurred at the Zr/Ta interface when the hydrogen concentration of Ta was over 20 ppm, and the ductility of the specimens with such hydrogen concentration was recovered when the hydrogen concentration of Ta decreased below 10 ppm by thermal aging at 300
C for 1000 hr, while the hydrogen concentration was reduced to The ductility of the Ta/Zr interface was not recovered without significant decrease in hydrogen concentration. These results suggest that the hydrogen concentration in Ta at the Ta/Zr interface affects the hydrogen embrittlement behavior of the explosion joint and that the hydrogen state changes with thermal aging.
Zn
Y
Harjo, S.; Aizawa, Kazuya; Gong, W.*; Kawasaki, Takuro; Yamasaki, Michiaki*; Kawamura, Yoshihito*
no journal, ,
no abstracts in English