Enrichment and in-situ ceramic immobilization of uranium by mesoporous ZrO2/SBA-15
Enrichment and in-situ ceramic immobilization of uranium by mesoporous ZrO2/SBA-15
复制标题
DOI：
10.1016/j.ceramint.2021.08.200
复制
发表时间：
2021-08
影响因子：
5.2
通讯作者：
Yi Ding;W. Fan;Zhenyu Chen;Zhen Li;Yuan Liu;Hui Dan;Tao Duan
中科院分区：
文献类型：
--
作者：
Yi Ding;W. Fan;Zhenyu Chen;Zhen Li;Yuan Liu;Hui Dan;Tao Duan
为了简化放射性废水的处理，减少二次污染，本文首次合成了介孔ZrO2/SBA-15，并将其作为吸附剂和结晶基质用于放射性废水中U的高效富集和原位固定化。一般来说，利用介孔ZrO2/SBA-15富集U，然后通过后续烧结工艺将U固定在zrsio4陶瓷中。在1250 ~ 1450℃下烧结6 h，将吸附了U的ZrO2/SBA-15转变为稳定的ZrSiO4-U陶瓷，并通过取代Zr（Ⅳ）将U（Ⅳ）和Ⅵ纳入zrsio4的晶体结构。此外，得到的ZrSiO4-U陶瓷具有良好的水性耐久性。ZrO2/SBA-15具有较高的吸附能力和良好的水耐久性，有望在含铀放射性废水的处理中得到实际应用。
To simplify the treatment of radioactive wastewater and reduce the secondary pollution, in this work, mesoporous ZrO2/SBA-15 was synthesized and employed for the first time as both the adsorbents and crystalline matrices for efficient enrichment and in-situ immobilization of U in radioactive wastewater. In general, U was efficiently enriched by using the mesoporous ZrO2/SBA-15 and then immobilized into ZrSiO4ceramics by the followed sintering process. The U-adsorbed ZrO2/SBA-15 was changed to stable ZrSiO4–U ceramics by sintering at 1250–1450 °C for 6 h. The results also provided the evidence that both U(Ⅳ) and (Ⅵ) were incorporated into the crystal structure of ZrSiO4by replacing Zr(Ⅳ). Furthermore, all the obtained ZrSiO4–U ceramics exhibited good aqueous durability. Given the high adsorption capacity and good aqueous durability, it is expected that the ZrO2/SBA-15 is attractive for actual applications in treatment of U containing radioactive wastewater.