四钛酸钾晶须处理含铀废水实验研究

Treatment of Uranium-bearing Wastewater Using Potassium Tetratitanate Fiber

实验研究新型无机离子交换剂——四钛酸钾晶须(K2Ti4O9)处理含铀废水。通过静态交换实验优化影响铀去除率的因子,并测定四钛酸钾晶须对铀的饱和交换容量;利用制备的四钛酸钾-PVC膜进行动态交换实验;初步实验研究了四钛酸钾在不同温度和配方下的烧结固化。结果表明,在酸性条件下,四钛酸钾对铀的去除率>95%,最佳pH为3～4,对铀的静态饱和交换容量约为894μg/g;制备的四钛酸钾-PVC膜对铀的动态交换容量约为185μg/g;80%K2Ti4O9+20%高岭土在1200℃下烧结效果良好。

A new inorganic ion-exchanger of potassium tetratitanate fiber for treating uranium-bearing wastewater was introduced,and effect of different ion-exchanging conditions on uranium removal was examined. The sinter of K2Ti4O9 and kaoline under different temperatures was prepared,and experimental results showed that removal efficiency of uranium up to 95% was achieved at optimum condition of pH 3~4. The penetrating capacity of PVC membrane embedded with K2Ti4O9 for uranium was 185μg/g. The sinter of 80% K2Ti4O9 and 20% kaoline prepared at 1200℃ had good effect.