铀污染过滤器芯钙钛锆石玻璃陶瓷固化研究

Immobilization of filter-paper polluted by uranium on zirconolite-based glass-ceramics

以B2O3、CaO、TiO2和ZrO2为固化原料,以Ce作为铀的模拟核素,开展了铀污染过滤器芯钙钛锆石玻璃陶瓷固化体的影响因素研究,利用XRD、SEM、ICP-MS等分析方法对固化体进行了结构性能表征。研究结果表明,通过向铀污染过滤器芯中添加成核剂可以形成钙钛锆石玻璃陶瓷固化体,其最佳晶化温度约为1 050℃;钙钛锆石玻璃陶瓷中晶体的形成与B2O3、TiO2及ZrO2添加量密切相关,其最佳含量分别为8.09%、9.17%和7.05%;钙钛锆石玻璃陶瓷固化体中Ce元素的归一化浸出率低于10-10g·cm-2·d-1数量级,固化体对模拟核素Ce具有良好的包容性能。

Zirconolite-based glass-ceramics was prepared using B2 O3 ,CaO,TiO2 and ZrO2 as raw materials with melting method for disposal of U-containing Filter-paper. The samples were characterized by means of XRD,SEM,ICP-MS,etc. The results indicated that Zirconolite crystal formation have advantages on the condition of the crystallization on 1050℃,8. 09%wt B2 O3 ,9. 17%wtTiO2 and 7. 05%wtZrO2 in the glass-ceramics. The leaching results with Ce as simulating nuclides for glass-ceramics show that the nor-malized leaching rates of Ce are lower with the magnitude of 10-10 g·cm-2·d-1 and the Zirconolite-based glass-ceramics have better encapsulation capacity for Ce as simulating nuclides.