Effect of Helium on Dispersoid Evolution under Self-Ion Irradiation in A Dual-Phase 12Cr Oxide-Dispersion-Strengthened Alloy
Effect of Helium on Dispersoid Evolution under Self-Ion Irradiation in A Dual-Phase 12Cr Oxide-Dispersion-Strengthened Alloy
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DOI：
10.3390/ma12203343
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发表时间：
2019-10
期刊：
影响因子：
3.4
通讯作者：
Hyosim Kim;Tianyao Wang;J. Gigax;S. Ukai;F. Garner;L. Shao
中科院分区：
文献类型：
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作者：
Hyosim Kim;Tianyao Wang;J. Gigax;S. Ukai;F. Garner;L. Shao
研究了一种具有高温强度和抗蠕变性能的双相12Cr氧化物弥散强化（ODS）合金，作为未来第四代反应堆和聚变反应堆的候选合金，在高温高损伤自离子辐照下表现出良好的抗空隙膨胀性能。然而，氦及其与辐射损伤的结合对氧化物分散体稳定性的影响还有待进一步研究。本研究在室温下分别以1 × 1015和1 × 1016离子/cm2的剂量预加载120 keV能量的氦，在475℃下依次注入3.5 MeV的Fe自离子，使其达到每原子100个峰值位移。在对照样品中单独植入对分散形态没有影响。Fe离子辐照后，低He剂量下相干氧化物分散体密度显著增加，高He剂量下无明显增加。该研究表明，氦气泡充当了相干氧化物分散体成核的汇，但如果引入太多的汇，分散体的生长可能会变得困难，这表明稳定的分散体生长需要临界质量的捕获。
As one candidate alloy for future Generation IV and fusion reactors, a dual-phase 12Cr oxide-dispersion-strengthened (ODS) alloy was developed for high temperature strength and creep resistance and has shown good void swelling resistance under high damage self-ion irradiation at high temperature. However, the effect of helium and its combination with radiation damage on oxide dispersoid stability needs to be investigated. In this study, 120 keV energy helium was preloaded into specimens at doses of 1 × 1015 and 1 × 1016 ions/cm2 at room temperature, and 3.5 MeV Fe self-ions were sequentially implanted to reach 100 peak displacement-per-atom at 475 °C. He implantation alone in the control sample did not affect the dispersoid morphology. After Fe ion irradiation, a dramatic increase in density of coherent oxide dispersoids was observed at low He dose, but no such increase was observed at high He dose. The study suggests that helium bubbles act as sinks for nucleation of coherent oxide dispersoids, but dispersoid growth may become difficult if too many sinks are introduced, suggesting that a critical mass of trapping is required for stable dispersoid growth.