放电等离子烧结
材料科学
辐照
氦
SPARK(编程语言)
等离子体
烧结
化学工程
复合材料
原子物理学
核物理学
计算机科学
物理
工程类
程序设计语言
作者
Stéphane Gavarini,J. Baillet,N. Millard-Pinard,V. Garnier,C. Peaucelle,Xavier Jaurand,C. Bernard,R. Rapegno,S. Cardinal,Charline Dalverny,B. Lanfant,Y. Leconte
标识
DOI:10.1016/j.jeurceramsoc.2019.09.018
摘要
Silicon carbide has a high resistance to irradiation making it a material of choice for use in the nuclear reactors. In this work, we focus on experiments involving implantation of 30 keV 3He ions at room temperature (RT) in sintered β-SiC. Helium is produced in large quantities in fission and fusion reactors, and its accumulation in materials can lead to the formation of bubbles. The irradiation induces structural modifications within the material that can be coupled with changes in composition, especially at high fluence. Three ion fluencies are used here: 5 × 1015, 1 × 1017and 1 × 1018at. cm−2. Structural damages are studied by electron microscopy and helium profiles are measured by nuclear reaction analysis (NRA). At 1 × 1018 at. cm−2, helium bubbles are formed in the implanted zone, which also undergoes strong oxidation. Surface blisters are also observed and helium concentration threshold for bubble formation is estimated to about 4 at. % by correlating the MET observations with the results obtained by ion beam analysis. For the highest fluence, a residual concentration of 3.6 × 1017 at. cm−2 was measured just after implantation (instead of 1 × 1018 at. cm−2), which indicates a significant release of helium by the material during the process. The link between the microstructural evolution of the material, its progressive oxidation under beam and the release of helium is discussed. The very likely role played by the porosity on the oxidation of the material under irradiation at RT is underlined. Finally, the results obtained here on silicon carbide are compared with those obtained on another ceramic (TiC) which does not amorphize in similar conditions.
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