Effects of Zr/Mo addition on He bubble formation in Y2O3-added W alloys
Effects of Zr/Mo addition on He bubble formation in Y2O3-added W alloys
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DOI：
10.1007/s42864-021-00131-4
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发表时间：
2022-01
期刊：
影响因子：
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通讯作者：
Qiu Xu;M. Miyamoto;L. Luo
中科院分区：
文献类型：
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作者：
Qiu Xu;M. Miyamoto;L. Luo
为了提高添加Y2O3的W合金的机械性能，在W-Y2O3样品中分别添加Mo和Zr。本研究在 773 K、973 K 和 1173 K 温度下研究了少量添加元素 Mo 和 Zr 对添加 Y2O3 的 W 合金中 He 气泡形成的影响，其中使用 5 keV He 离子的样品的最大辐照通量为 1.8 × 1021He m−2。两种合金在所有温度下均观察到气泡；然而，在每个温度下可以观察到氦气泡的辐照通量有所不同。随着辐照温度的升高，可观察到He气泡形成的He辐照注量降低。在 773 K 的相对较低温度下，W-Mo-Y2O3 和 W-Zr-Y2O3 合金的空洞膨胀略低于 W-Y2O3 合金。然而，在973 K和1173 K高温下，W-Mo-Y2O3和W-Zr-Y2O3的耐He辐照性能都比W-Y2O3差。 Zr的添加增强了空位与He之间的相互作用，促进了He气泡的形成。然而，Mo的添加使Y2O3颗粒粗化，降低了由于Y2O3颗粒分散而对空位簇形成的抑制。因此，除了He的耐辐照性之外，还必须充分考虑机械性能和T保留，以选择合金作为聚变应用的面向等离子体材料。
To improve the mechanical properties of the Y2O3-added W alloy, Mo and Zr were independently added to a sample of W-Y2O3. In this study, the effects of minor additions of elemental Mo and Zr on He bubble formation in the Y2O3added W alloys were investigated at 773 K, 973 K, and 1173 K, where the maximum irradiation fluence of the samples using 5 keV He ions was 1.8 × 1021He m−2. He bubbles were observed at all temperatures for both alloys; however, the irradiation fluences at which He bubbles could be observed differed at each temperature. With increase in irradiation temperature, the He irradiation fluence for which the formation of He bubbles could be observed decreased. At the relatively low temperature of 773 K, the void swelling in the W-Mo-Y2O3and W-Zr-Y2O3alloys was slightly lower than that of W-Y2O3alloy. However, at high temperature of 973 K and 1173 K, the He irradiation resistances of both W-Mo-Y2O3and W-Zr-Y2O3were worse than that of W-Y2O3. The addition of Zr enhanced the interaction between vacancies and He, enhancing the formation of He bubbles. However, the addition of Mo coarsened the Y2O3particles, reducing the suppression of vacancy cluster formation due to the dispersion of Y2O3particles. It is, therefore, necessary to fully consider mechanical properties and T-retention in addition to the irradiation resistance of He to select an alloy as the plasma-facing material for fusion applications.