模拟结构用混凝土核废物高温熔融处理研究  

High Temperature Melting Treatment of Simulated Structural Concrete Nuclear Waste

作　　者：刘春雨 袁誉坤 李丽丽 方广 徐凯[2] LIU Chunyu;YUAN Yukun;LI Lili;FANG Guang;XU Kai(Department of Radioactive Waste Technology and Radiochemistry Research,China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen 518028,China;State Key Laboratory of Silicate Materials for Architectures,Wuhan University of Technology,Wuhan 430070,China)

机构地区：[1]中广核研究院有限公司放废与放化研究所,深圳518028 [2]武汉理工大学硅酸盐建筑材料国家重点实验室,武汉430070

出　　处：《硅酸盐通报》2023年第8期2781-2786,共6页Bulletin of the Chinese Ceramic Society

基　　金：国家重点研发计划(2018YFB1900203)。

摘　　要：核设施退役过程中会产生大量污染或活化的低放射性混凝土核废物,相比于传统的水泥固化,玻璃材料因对放射性元素包容广、化学稳定性优良而被广泛应用于固化处理放射性废物。本文通过高温熔融的方法玻璃固化处理模拟结构用混凝土核废物,在混凝土中添加一定量玻璃添加剂(包括SiO_(2)、B_(2)O_(3)及Na_(2)O,其在玻璃固化体中质量分数分别为~26%、~13%及~6%),于1300℃下将混凝土核废物转化为熔融态玻璃,获得的玻璃固化体化学稳定性满足国际低放废物固化体处置抗浸出标准,同时分析了模拟核素在高温熔融过程中的挥发行为及在固化体中的赋存状况。本研究可为混凝土核废物熔融固化提供基础数据支持。A large amount of low-level radioactive concrete nuclear waste with contamination and activation will be generated when the nuclear facilities are decommissioned.Glass material has been used to immobilize kinds of radioactive wastes because of its wide incorporation to radioactive elements and excellent chemical durability,compared with traditional cement solidification.In this paper,the simulated structural concrete nuclear waste was treated by high temperature melting.The concrete was vitrified with the glass additive(~26%(mass fraction)SiO_(2),~13%(mass fraction)B_(2)O_(3)and~6%(mass fraction)Na_(2)O)at 1300℃,and the chemical durability of thus resulted glass waste form meets the disposal requirements for low-level waste form.The volatilization behavior of the simulated nuclides at high temperature and their local structure in the glass were finally discussed.The results can provide the basic information to vitrify the concrete nuclear waste.

关 键 词：核设施退役 放射性固体废物 混凝土 玻璃固化 化学稳定性 挥发 

分 类 号：TL941[核科学技术—辐射防护及环境保护]