摘要
采用自蔓延高温合成技术制备核废物固化体,并实验研究钙钛矿固化体对锶核素(Sr2+)的最大包容量。通过X射线衍射、扫描电镜和浸出法分析了该固化体的物相组成、微观结构和化学稳定性。结果表明:钙钛矿固化体对SrO的包容量可达到36%(质量分数),且产物成分均匀,浸出率低,化学稳定性好,是固化锶核素废物的理想固化体。
High level waste （HLW） loaded wasteforms were prepared by self-propagating high-temperature synthesis, and the maximum loading of Sr^2＋ for perovskite wasteform was investigated. The phase compositions, microstructure and chemical durability of wasteforms were tested by X-ray diffraction, scanning electric microscopy and the leaching method. The results show that the perovskite wasteform is the perfect material to immobilize the HLW SrO. The maximum loading of SrO in the wasteform can reach 36% in mass fraction with a low leaching rate and good durability.
出处
《硅酸盐学报》
EI
CAS
CSCD
北大核心
2005年第8期1045-1048,共4页
Journal of The Chinese Ceramic Society
基金
国家自然科学基金(20476008)资助项目
关键词
钙钛矿
物相组成
锶核素废物
固化
自蔓延高温合成
准等静压方法
perovskite
phase composition
strontia nuclear waste
immobilization
self-propagating high-temperature synthesis
pseudo isostatic pressing method
