分离-固化是处理高放废液的良好策略之一。然而，现有工艺是先用不易固化处理的吸附材料对相应核素分离，再用特定固化基材对分离后的核素固化，存在步骤复杂及二次污染问题。本项目利用易于固化处理的介孔ZrO2/SBA-15材料实现锕系核素的分离富集-原位固化处理，并探索相应吸附及固化机理。研究ZrO2掺杂量、P123用量、硅源浓度、酸度、温度及时间等对材料组成、微观结构、自组装行为及初始颗粒生长机制的影响；探讨ZrO2/SBA-15组成、微观结构及吸附条件等对核素分离富集行为的影响，揭示其吸附机理；研究核素在介孔材料中的吸附占位与固化体中的晶格占位间的演变规律，分析核素在固化体中的固溶极限、适应性及赋存状态（价态、占位及竞争机制等），探讨固化体致密化机制，阐明核素原位固化机理；在模拟地质处置库溶液环境下，研究固化体的溶解及浸出行为，评价化学稳定性。预期研究成果将为高放废液的有效处理和处置提供新思路。

Separation-immobilization is one of the good strategies for the treatment of radioactive wastewater. However, the existing separation-immobilization process is to separate radionuclides using adsorbents and then immobilize them with waste form materials. Currently, the commonly used adsorbents are not easily treated to form waste forms. This will lead to the complex treatment steps and secondary contamination. In this project, mesoporous ZrO2/SBA-15 material, which is easy to be immobilized, is used to separate, enrich and in-situ immobilize the actinides, and the adsorption and immobilization mechanism are explored. The effects of ZrO2 content, acidity, synthetic temperature and template amount on the composition, microstructure and self-assembly behavior of mesoporous SBA-15 are investigated. The effects of the composition and microstructure of mesoporous ZrO2/SBA-15 and adsorption conditions on the adsorption behavior of actinides are studied, and the adsorption mechanism is revealed. The evolution of nuclide adsorption sites in mesoporous materials and lattice sites in ceramic waste forms is investigated. The immobilization limit, occurrence state (valence state, occupancy and competition mechanism) and adaptability of nuclides in waste forms are investigated, and the The densification mechanism of waste forms and immobilization mechanism of actinides are clarified. Under the simulated geological repository solution environment, the dissolution and leaching behavior of waste forms were studied and their chemical stability was evaluated. It is expected that the research results will provide new ideas for the effective treatment and disposal of high-level radioactive waste water.