模拟锕系高放废液铁磷酸盐玻璃陶瓷固化  

Solidification of Simulated α-HLLW in Iron Phosphate Glass Ceramics

作　　者：潘社奇[1] 苏伟[1] 赵玉杰[1] 陈晓谋[1] 王东文[1] 

机构地区：[1]中国工程物理研究院,四川绵阳621900

出　　处：《环境科学与技术》2014年第6期64-67,共4页Environmental Science & Technology

基　　金：国家自然科学基金资助(91126015)

摘　　要：采用铁硼磷酸盐玻璃对TRPO流程分离后产生的富锕系核素模拟废物进行了固化研究,并用X射线衍射(XRD)和试样坚固法(PCT)测试了所制备试样的结构与化学稳定性。结果表明:在930℃的烧结温度下、保温2 h,可获得结构致密、结晶程度较好的玻璃陶瓷固化体,试样中的主晶相为独居石;固化体中模拟高放废物含量对其结构和化学稳定性均有影响,此工艺条件下模拟废物的包容量最高可达25%,对应的固化体中Fe、P和Ce元素的浸出率分别为28.10×10-4、56.61×10-4和0.95×10-4g/(m2·d),试样的化学稳定性较好。Iron boron phosphate glass was used for immobilization simulating et-HLLW, and results showed that sintering at a temperature of 930 ℃, heating for 2 h, monazite-typed crystal was detected only by XRD apparatus in the solidification. The samples, containing different contents of simulated α-HLLW, were measured by product consistency test （PCT）, showed the maximum pack capacity up to 25% with a good chemical durability, and the normalized elemental mass release of Fe, P, Ce is 28.10×10^-4, 56.61×10^-4 and 0.95×10^-4 g/（m^2·d）.

关 键 词：高放废液 铁磷酸盐玻璃 固化 

分 类 号：X591[环境科学与工程—环境工程] TL941[核科学技术—辐射防护及环境保护]