用原子力显微镜研究锆合金离子辐照引起的表面损伤特征

IF 2.2 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Materials Letters: X Pub Date : 2022-03-01 DOI:10.1016/j.mlblux.2022.100125
Fusheng Li, Shilei Li, Peng Wang, Yanli Wang
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引用次数: 0

摘要

在锆-4合金中进行了400°C连续Kr离子辐照,损伤程度高达40dpa,以研究α-Zr基体的表面损伤特征。原子力显微镜证实,辐照引起的表面损伤主要以损伤凹坑的形式存在。Ra值的增加表示随着连续照射而逐渐的表面粗糙化过程。辐照引起的表面粗糙化机制分为三个阶段:第一阶段,低剂量下损伤凹坑沿深度方向的形成和生长;第二阶段,表面内受损区域的扩展;第三阶段,一旦未损坏的基质耗尽,就逐层去除表面原子。
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Investigations of ion irradiation induced surface damage features in zirconium alloys by atomic force microscopy

Continuous Kr ion irradiation at 400 °C with damage level up to 40 dpa was performed in Zircaloy-4 to investigate the surface damage features of α-Zr matrix. Atomic force microscopy confirms that the irradiation induced surface damage is primarily in the form of damaged pits. The increasing Ra value indicates the gradual surface roughening process with continuous irradiation. The irradiation-induced surface roughening mechanism is suggested as three stages: stage I, the formation and growth along depth direction of damaged pits at low doses; stage II, the extension of damaged region within the surface; stage III, layer by layer removal of surface atoms once the undamaged matrix is depleted.

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来源期刊
CiteScore
3.10
自引率
0.00%
发文量
50
审稿时长
114 days
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