当前位置: X-MOL 学术J. Nucl. Mater. › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
Heavy ion irradiation damage in Zr3(Al0.9Si0.1)C2 MAX phase
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2020-07-02 , DOI: 10.1016/j.jnucmat.2020.152360
Hassan H. Qarra , Kevin M. Knowles , Mary E. Vickers , Eugenio Zapata-Solvas , Shavkat Akhmadaliev

A Zr3(Al0.9Si0.1)C2 MAX phase-based ceramic with 22 wt.% ZrC and 10 wt.% Zr5Si3 has been irradiated with 52 MeV I9+ ions at room temperature, achieving a maximum dose of 8 displacements per atom (dpa). The response of this MAX phase-rich material to irradiation has been studied using scanning electron microscopy, transmission electron microscopy and X-ray diffraction techniques. Post-irradiation examination of the material revealed a number of crystalline changes to the MAX phase. At low doses, Zr3(Al0.9Si0.1)C2 maintained a high degree of crystallinity, while at the highest doses, its degree of crystallinity was reduced significantly. A number of radiation-induced phase transformations were observed, including the decomposition of Zr3(Al0.9Si0.1)C2 into ZrC and other phases, and the formation of β-Zr3(Al,Si)C2, a MAX phase with a rearranged stacking sequence. Microstructural examination revealed that the majority of the extended defects in Zr3(Al0.9Si0.1)C2 lie in the (0001) basal planes. Analysis of X-ray diffraction profiles after heat treating the 8 dpa-irradiated material for 1 h at 300 °C and at 600 °C showed that there were only subtle changes to the profiles relative to that of the 8 dpa-irradiated material which had not been heat treated. Overall, the experimental results of this study show that the Zr3(Al0.9Si0.1)C2 MAX phase responds less well to irradiation relative to other MAX phases irradiated with high energy heavy ions at room temperature.



中文翻译:

Zr 3(Al 0.9 Si 0.1)C 2 MAX相的重离子辐照损伤

已在室温下用52 MeV I 9+离子辐照Zr 3(Al 0.9 Si 0.1)C 2 MAX相基陶瓷,该陶瓷具有22 wt。%的ZrC和10 wt。%的Zr 5 Si 3。每个原子8个位移(dpa)。已经使用扫描电子显微镜,透射电子显微镜和X射线衍射技术研究了这种MAX富相材料对辐照的响应。对该材料进行辐照后检查显示,MAX相发生了许多结晶变化。低剂量时Zr 3(Al 0.9 Si 0.1)C 2保持较高的结晶度,而在最高剂量下,其结晶度显着降低。观察到许多辐射诱导的相变,包括Zr 3(Al 0.9 Si 0.1)C 2分解为ZrC和其他相,以及形成β- Zr 3(Al,Si)C 2,即MAX相。重新排列的堆叠顺序。显微组织检查表明,Zr 3(Al 0.9 Si 0.1)C 2的大部分扩展缺陷位于(0001)基础平面中。在300°C和600°C下对8 dpa辐照的材料进行热处理1 h后的X射线衍射图分析表明,相对于8 dpa辐照的材料,X射线衍射图谱仅发生了细微变化。未经热处理。总体而言,这项研究的实验结果表明,与在室温下用高能重离子辐照的其他MAX相相比,Zr 3(Al 0.9 Si 0.1)C 2 MAX相对辐照的响应较差。

更新日期:2020-08-01
down
wechat
bug