D2 retention behavior and microstructural evolution of W-2wt.%Y2O3 alloy during He-ion irradiation at high temperatures
D2 retention behavior and microstructural evolution of W-2wt.%Y2O3 alloy during He-ion irradiation at high temperatures
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DOI:
10.1016/j.jnucmat.2020.152273
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发表时间:
2020-06
影响因子:
3.1
通讯作者:
Qiu Xu;L. Luo;Z. Chen;M. Hirakawa;M. Miyamoto;Hongyingnan Chen;Koichi Sato;H. Tsuchida
中科院分区:
文献类型:
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作者:
Qiu Xu;L. Luo;Z. Chen;M. Hirakawa;M. Miyamoto;Hongyingnan Chen;Koichi Sato;H. Tsuchida
In this study, we carried out the pre-irradiation of a dispersion-strengthened W-2wt.%Y2O3alloy with good mechanical properties with high-energy Fe-ions instead of neutrons. The effect of this pre-irradiation on the D2retention behavior of the alloy was investigated. A maximum of 1022D/m2was irradiated onto the samples using 5-keV D2ions, and Fe pre-irradiation was carried out up to an ion fluence of 4 × 1018/m2with 1 MeV energy. For comparison, commercial pure W was also studied. The Fe-ion pre-irradiation process increased the D2retention in both pure W and the W–Y2O3alloy. However, this D2retention was independent of the pre-irradiation dose. In addition, the formation of He bubbles in the W–Y2O3alloy caused by the irradiation at 1.8 × 1021He/m2and high temperatures of 773, 973, and 1173 K was also investigated. When the irradiation dose exceeded 1.5 × 1020He/m2, visible He bubbles were formed, and He bubbles grew and void swelling increased with an increase in the irradiation dose. Compared to pure W, the W–Y2O3alloy showed suppressed void swelling. This can be attributed to the dispersion of vacancies and He atoms due to the He irradiation.