低中放废物玻璃固化体性能要求及测试方法探讨  

Investigation on performance requirements and test methods of low and intermediate vitrified radioactive waste

作　　者：甘学英 徐春艳 方岚 汪世军 何玮 刘新华 GAN Xueying;XU Chunyan;FANG Lan;WANG Shijun;HE Wei;LIU Xinhua(Nuclear and radiation Safety Center,Ministry of Ecology and Environment,Beijing 100082)

机构地区：[1]生态环境部核与辐射安全中心,北京100082

出　　处：《辐射防护》2021年第1期50-57,共8页Radiation Protection

基　　金：大型先进压水堆及高温气冷堆核电站国家科技重大专项《先进压水堆便于退役的要求研究》(编号:2018ZX06002005)资助。

摘　　要：为了减少废物体积,提升废物处置安全,将玻璃固化技术用于低中放废物的处理。低中放废物玻璃固化体性能要求及测试方法,我国目前缺少相应的标准。本文通过废物固化体标准和公开发表的相关测试数据对比分析,给出了低中放废物玻璃固化体的性能要求和测试方法的建议。Vitrification technologies were applied in the treatment of low and intermediate-level radioactive wastes for waste volume reduction and the improvement of waste disposal safety.The relevant standard of performance requirements and test methods for the low and intermediate vitrified radioactive waste are absence in China currently.The performance requirements and test methods were suggested by comparison analysis with several waste form standards and some relevant published test data.

关 键 词：低中放废物 玻璃固化体 浸出率 性能测试 

分 类 号：TL941+.113[核科学技术—辐射防护及环境保护]