Irradiation Damage in Ti3(Si,Al)C2: a TEM Investigation
Irradiation Damage in Ti3(Si,Al)C2: a TEM Investigation
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DOI：
10.1111/j.1744-7402.2010.02523.x
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发表时间：
2010-11
影响因子：
2.1
通讯作者：
M. L. Flem;Xingmin Liu;S. Doriot;T. Cozzika;I. Monnet
中科院分区：
文献类型：
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作者：
M. L. Flem;Xingmin Liu;S. Doriot;T. Cozzika;I. Monnet
属于MAX相的Ti 3SiC 2是一种潜在的候选材料，可用于未来的气冷快堆（GFR）堆芯部件。尽管大量的工作，机械性能，耐腐蚀性，或电气性能，数据有关的Ti 3SiC 2辐照下的演变是非常有限的。在本工作中，在室温下用92 MeV的正离子辐照Ti_3（Si，Al）C_2以引起辐照损伤。通过透射电子显微镜（TEM）通过正视图和横截面观察来研究样品，这允许跟踪从0.02 dpa到6.67 dpa的微观结构变化。突出显示了渐进的原子无序与剂量的关系，导致一些衍射斑点（在0.15 dpa）和扩散图案（在3 dpa）的消失。与3-1-2 MAX相位相关的ABABACAC周期丢失，但仍可识别基底平面的图像条纹，且未出现无定形环。这意味着Ti 3（Si，Al）C2受到辐射的强烈影响，但即使在6.67 dpa下也没有变成非晶。这一重要的结果是相关的X-射线衍射和纳米压痕分析的结论，并表明良好的行为Ti 3（Si，Al）C2在目标温度范围内分配到GFR的照射。
Ti3SiC2, belonging to MAX phases, is a potential candidate material, which could be incorporated in core components of future gas-cooled fast nuclear reactors (GFR). Despite extensive work on mechanical behavior, corrosion resistance, or electrical properties, data concerning the evolution of Ti3SiC2 under irradiation are very limited. In this work, Ti3(Si,Al)C2 was irradiated at room temperature with 92 MeV Xe ions to induce irradiation damage. The samples were investigated by transmission electron microscopy (TEM) through front view and cross-section observations, which allowed to follow microstructure changes from 0.02 dpa up to 6.67 dpa. Progressive atomic disorder versus dose was highlighted, leading to extinction of some diffraction spots (at 0.15 dpa) and then diffuse patterns (at 3 dpa). The ABABACAC periodicity related to 3-1-2 MAX phases was lost but the image fringes of basal plans could still be identified and no amorphous ring occurred. This means that Ti3(Si,Al)C2 was strongly affected by irradiation but did not turn to amorphous even at 6.67 dpa. This important result was correlated to previous conclusions from X-ray diffraction and nanoindentation analysis and suggests the good behavior of Ti3(Si,Al)C2 under irradiation in the target temperature range assigned to GFR.