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作 者:陈晓谋[1] 孟成[2] 张峰[1] 唐灿[1] 丁新更[2]
机构地区:[1]中国工程物理研究院,四川绵阳621900 [2]浙江大学,浙江杭州310027
出 处:《稀有金属材料与工程》2016年第S1期194-197,共4页Rare Metal Materials and Engineering
摘 要:通过X射线衍射仪和场发射电子显微镜研究钙钛锆石基玻璃陶瓷体的析晶行为和表面形貌。利用电感耦合等离子体质谱仪测试Ce元素的标准化抗浸出性能。结果表明:当CeO_2掺量(质量分数,下同)为0%~1%时,玻璃陶瓷体内形成了单斜相(CaZrTi2O7-2M)和六方相(CaZrTi2O7-3T)的钙钛锆石,当CeO_2掺量为3%~11%时,单斜相(CaZrTi2O7-2M)钙钛锆石消失,形成了单一的六方相(CaZrTi2O7-3T)的钙钛锆石,其晶胞参数、晶胞体积以及结晶度均随CeO_2掺量增加而增加。固化体的抗浸出性能表明,固化体可稳定存在于地质处置条件下,其28dCe元素浸出率为10–7g·m-2·d-1。The structure and microstructure of zirconolite-based glass-ceramics were characterized by XRD and SEM, respectively. The normalized release rate of Ce(NRCe) was measured by the ASTM Product Consistency Test(PCT) leaching method. Results show that when Ce O_2 content is ranged from 0wt% to 1wt%, two zirconolite crystals, monoclinic(CaZrTi_2O_7-2M) and hexagonal layered structure(CaZrTi_2O_7-2T), form in the bulk glass. When the content of Ce O_2 increases from 3 wt% to 11 wt%, the monoclinic layered structure phase disappears. The unit cell parameters and cell volume V of zirconolite phase(Ca Zr Ti2O7-2T) increase with the increase of Ce O_2 content. The leaching resistance shows that the solidified radioactive waste forms would be stable for the eventual geological disposal, and leaching rate of Ce^(3+) reaches 10-7 g·m-2·d-1 at 28 d.
分 类 号:TL941[核科学技术—辐射防护及环境保护]
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