90－19／U模拟高放废物玻璃固化体表面性能的研究  

CHARACTERIZATION OF 90-19/U HLW-GLASS SURFACE

作　　者：盛嘉伟[1] 罗上庚[1] 汤宝龙[1] 柳得撸 

机构地区：[1]中国原子能科学研究院,北京科技大学材料物理系

出　　处：《辐射防护》1996年第2期114-120,共7页Radiation Protection

摘　　要：本文对９０－１９／Ｕ模拟高放废物玻璃固化体的表面性能进行了研究。实验结果表明，固化体与水反应会导致固化体表面层的产生，表面层中Ｌｉ、Ｎａ、Ｂ等易溶元素发生贫化，而Ｕ、Ｆｅ、Ｔｉ、Ｍｇ、Ｃａ等元素发生不同程度的富集；随反应程度不同，表面层厚度也不同，且在反应进行至一定程度后，表面层会发生不同程度裂缝和脱落，并产生表面沉积物。The surface layer characterization of 90-19/U HLW-glass form subjected to static or dynamic leaching test for varied periods at different temperature has been studied. It wasrevealed that the reaction between glass and water resulted in the formation of a surface layer in which the easily soluble element such as Li,Na,B etc. were depleted and some elements such as U,Fe,Ti,Mg and Ca were enriched. The thickness of the surface layer increased with the progress of hydrolytic reaction of glass. After a certain period in the course of leachingtest fissuring and peeling took place on the surface layer,and amorphous and crystalline precipitates appeared on the surface of glass.

关 键 词：高放废物 玻璃固化体 表面层 表面性能 

分 类 号：TL941.113[核科学技术—辐射防护及环境保护]