高放废液中放射性铯的玻璃固化配方研究
Research Regarding Vitirfication of Radioactive Cs in High-level Liquid Waste
董海龙 1梁璇 1姚美玲1
作者信息
- 1. 中国核电工程有限公司,北京 100840;核退役治理技术创新中心,北京 100840
- 折叠
摘要
本文探讨了针对乏燃料后处理产生的高放废液中含有的潜在放射性毒性最大的放射性核素铯的采用玻璃、陶瓷、玻璃-陶瓷固化研究.首先介绍了高放废液的中放射性铯的产生来源和其相应的特点,并分析了放射性铯在处理处置过程中的衰变、释热原理和影响.通过目前国际上关于放射性铯的玻璃和陶瓷固化配方的研究进行了讨论,其中包含硅酸盐和磷酸盐玻璃,单相或多相陶瓷.特别介绍了荷兰石矿相用于固化放射性铯核素的研究.结合我国两步法冷坩埚玻璃固化技术的研究进展,分析了采用陶瓷相和玻璃-陶瓷相固化动力堆乏燃料后处理产生的高放废液中放射性铯同位素的适用性、面临的挑战和发展方向.
Abstract
This paper discussed processing radioactive Cs isotopes in Spent fuel reprocessing High-level liquid waste(HLLW),which have high potential radiotoxcity,using glass,ceramic or glass-ceramic vitrification.Firstly,the generation and character of radioactive Cs is introduced.The decay,heat generation theory and their influence during processing radioactive Cs are analyzed.Then the research about glass and ceramic consolidation of Cs around the world is discussed,including silicate and phosphate glass formulation also single and multi phase ceramic material.Specially the research regards Cs vitrification via hollandite is introduced.With developing of the two-steps cold-crucible vitrification technology,using ceramic and glass-ceramic phase to vitrificate radioactive Cs isotopes in Power reactor spent fuel reprocessing HLLW is becoming more suitable,which also facing challenges.
关键词
高放废液/放射性铯/荷兰石/两步法冷坩埚玻璃固化技术Key words
high-level liquid waste/radioactive Cs/hollandite/two-steps cold crucible Vitrificaion引用本文复制引用
出版年
2024
NETL
NSTL
万方数据