Nebraska Center for Energy Sciences Research, University of Nebraska-Lincoln, Lincoln, NE, 68583-0857, USA.
Department of Materials Science and Engineering, Kyushu Institute of Technology, Tobata, Kitakyushu, Fukuoka, 804-8550, Japan.
Sci Rep. 2017 Jun 20;7(1):3900. doi: 10.1038/s41598-017-04247-x.
Despite recent interest in amorphous ceramics for a variety of nuclear applications, many details of their structure before and after irradiation/implantation remain unknown. Here we investigated the short-range order of amorphous silicon oxycarbide (SiOC) alloys by using the atomic pair-distribution function (PDF) obtained from electron diffraction. The PDF results show that the structure of SiOC alloys are nearly unchanged after both irradiation up to 30 dpa and He implantation up to 113 at%. TEM characterization shows no sign of crystallization, He bubble or void formation, or segregation in all irradiated samples. Irradiation results in a decreased number of Si-O bonds and an increased number of Si-C and C-O bonds. This study sheds light on the design of radiation-tolerant materials that do not experience helium swelling for advanced nuclear reactor applications.
尽管最近人们对各种核应用的非晶陶瓷产生了兴趣,但它们在辐照/注入前后的许多结构细节仍然未知。在这里,我们通过电子衍射获得的原子配分函数(PDF)研究了非晶硅氧碳(SiOC)合金的短程有序。PDF 结果表明,SiOC 合金的结构在辐照高达 30 dpa 和 He 注入高达 113 at%后几乎没有变化。TEM 表征显示,所有辐照样品中均没有结晶、He 泡或空隙形成或偏析的迹象。辐照导致 Si-O 键数量减少,Si-C 和 C-O 键数量增加。这项研究为设计在先进核反应堆应用中不经历氦肿胀的耐辐射材料提供了思路。