摘要
以天然锆英石(ZrSiO4)、CaCO3、TiO2和UO2(NO3)2.6H2O为原料,通过高温固相反应,制备了包容铀(质量分数4.5%)的钙钛锆石和榍石基人造岩石固化体。借助X射线衍射(XRD)和扫描电子显微镜(SEM)研究了其矿相组成和微观结构。采用MMC-1静态浸泡法和γ射线辐照方法测定了其抗浸出性能和抗辐照性能。结果表明,制备钙钛锆石和榍石基固化体的最佳合成及烧结温度为1 290℃。所得固化体结构致密,有较好的抗浸出性和辐照稳定性。
The present paper aims to introduce the authors＇ newly developed approach to safe and secure solidification of the nuclear waste including that of uranium. Using natural zirconite （ZrSiO4）, CaCO3, TiO2 and UO2 （NO3） 2·6H2O as raw materials, we have synthesized the zirconolite and titanite synroc solidification loaded with uranium（4.5wt% ） on the condition of a high temperature solid-phase reaction in our experiments. The phase assemblage and microstructure have also been investigated through the analysis of XRD and SEM. In addition, a chemical durability test has also been done with the MMC-1 method while the radiation stability of solidification phase is determined through γ radial irradiation. The results gained from the experiments prove that the optimum sinter and synthesis temperature of zirconolite and titanite synroc solidification to be 1 290℃. While the synroe solidification can keep a compact structure and a quite stable radiation rate, the leach rate of uranium is only 0.8 × 10^-8 cm/d in 102nd day, which suggests that the rate of the synroc solidification with uranium （4.5wt % ） is very. low and the synroc solidification has a proper chemical durabihty. And, therefore, the suggested approach of the present solid phase synthesis proves easier - done than that of liquid one. Thus, the present approach can be conducted in the experiments with raw materials, and hence easier to get access to and cheaper in consumption, and in turn more suitable to the engineering application.
出处
《安全与环境学报》
CAS
CSCD
2006年第4期115-117,共3页
Journal of Safety and Environment
基金
国家自然科学基金(中国工程物理研究院联合基金部分)资助项目(10176025)
关键词
辐射防护与环境保护
钙钛锆石
榍石
铀
固化
radiation protection and environmental protection
zirconolite
titanite
uranium
solidify
