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D2 retention behavior and microstructural evolution of W-2wt.%Y2O3 alloy during He-ion irradiation at high temperatures
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2020-06-22 , DOI: 10.1016/j.jnucmat.2020.152273
Q. Xu , L.M. Luo , Z. Chen , M. Hirakawa , M. Miyamoto , H.Y. Chen , K. Sato , H. Tsuchida

In this study, we carried out the pre-irradiation of a dispersion-strengthened W-2wt.%Y2O3 alloy with good mechanical properties with high-energy Fe-ions instead of neutrons. The effect of this pre-irradiation on the D2 retention behavior of the alloy was investigated. A maximum of 1022 D/m2 was irradiated onto the samples using 5-keV D2 ions, and Fe pre-irradiation was carried out up to an ion fluence of 4 × 1018/m2 with 1 MeV energy. For comparison, commercial pure W was also studied. The Fe-ion pre-irradiation process increased the D2 retention in both pure W and the W–Y2O3 alloy. However, this D2 retention was independent of the pre-irradiation dose. In addition, the formation of He bubbles in the W–Y2O3 alloy caused by the irradiation at 1.8 × 1021 He/m2 and high temperatures of 773, 973, and 1173 K was also investigated. When the irradiation dose exceeded 1.5 × 1020 He/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–Y2O3 alloy showed suppressed void swelling. This can be attributed to the dispersion of vacancies and He atoms due to the He irradiation.



中文翻译:

W-2wt。%Y 2 O 3合金在高温He离子辐照下的D 2保留行为和组织演变

在这项研究中,我们用高能Fe离子代替中子对具有良好机械性能的弥散强化W-2wt。%Y 2 O 3合金进行了预辐照。研究了这种预辐照对合金D 2保留行为的影响。使用5-keV D 2离子最多照射10 22 D / m 2到样品上,并使用1 MeV能量对Fe进行预辐射,直到离子通量达到4×10 18 / m 2为止。为了比较,还研究了商业纯W。Fe离子预辐照过程增加了纯W和W–Y 2 O中D 2的保留3合金。然而,该D 2保留与照射前剂量无关。此外,还研究了由W × Y 2 O 3合金在1.8×10 21 He / m 2的辐照以及773、973和1173 K的高温下引起的He气泡的形成。当照射剂量超过1.5×10 20 He / m 2时,形成可见的He气泡,并且随着照射剂量的增加,He气泡增大并且空隙膨胀增加。与纯W相比,W-Y 2 O 3合金显示出抑制的溶胀。这可以归因于由于He辐射而导致的空位和He原子的分散。

更新日期:2020-07-06
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