模拟高放废液玻璃固化体热学性能

Thermal properties of simulated high level liquid waste glass solids

玻璃固化技术是目前国内外HLW(高放废液)固化处理最主要的手段。高放废液中含有镧和铀,但镧、铀对固化工艺的影响鲜有报道。为对比镧、铀对玻璃固化体熔制工艺和产品性能的影响,分析不同镧铀比例下的各方面差异,以模拟高放废液的硼硅酸盐玻璃固化体作为实验材料,采用XRD(X射线衍射)、SEM(扫描电子显微镜)等表征方法研究玻璃固化体在不同热处理温度下的析晶行为和热稳定性。结果表明:在800、900、1000℃下,不同镧/铀配比的样品外观差别不大,热处理实验证实固化体样品在800—900℃热处理温度内有晶体析出,其中800℃热处理温度析晶最为严重。

Glass solidification technology is currently the main method for solidification and disposal of HLW(high-level radioactive waste)both domestically and internationally.High level radioactive waste contains lanthanum and uranium,but the impact of lanthanum and uranium on the solidification process has not been reported.In order to compare the effects of lanthanum and uranium on the melting process and product properties of the glass solidified body,and analyze the differences in various aspects under different lanthanum uranium ratios,borosilicate glass solidified bodies simulated from high-level radioactive waste were used as experimental materials,and characterization methods such as XRD(X-ray diffraction)and SEM(scanning electron microscopy)were used to study the crystallization behavior and thermal stability of glass solidified bodies at different heat treatment temperatures.The results show that there is little difference in the appearance of samples with different lanthanum/uranium ratios at 800,900,1000℃.Heat treatment experiments confirm that the solidified samples have crystal precipitation within the temperature range of 800-900℃.The crystallization is most severe within the temperature range of 800℃heat treatment.