【摘要】 以SiO2、Al2O3、B2O3、CaO、Na2O为原料,加入5%CeO2(质量分数)作为模拟核素,利用熔融法制备硼硅酸盐玻璃固化体,对含锕系元素的放射性废物进行固化处置。通过傅里叶红外光谱仪、紫外激光拉曼光谱仪和差热分析仪等对热处理后玻璃固化体进行表征,以电感耦合等离子体质谱测试玻璃固化体抗浸出性能。结果表明:B2O3含量为15.79wt%时固化体玻璃化转变温度Tg最大;玻璃中存在[SiO4]、[BO3]、[BO4]等基团,随着B2O3含量的增大,部分[BO4]转变为[BO3];Ce在产品一致性测试法(PCT)下标准化浸出率NR先减小后增大,B2O3含量达到15.79wt%时玻璃抗浸出效果最好。更多还原

【Abstract】 Borosilicate glass for vitrification of high level nuclear waste(HLW) were prepared with SiO2,Al2O3,B2O3,CaO,Na2O and 5wt% CeO2 by conventional solid-state method.The chemical durability of the glass waste forms was measured by Product Consistency Test(PCT) and the leaching rate was analyzed via inductively coupled plasma mass spectra.Fourier turning infrared spectroscopy and Laser Raman spectroscopy were also used in order to analyze the structure of glass waste forms.The results show that ,and exist in the glass waste forms and some turn into as B2O3 content increases.The glass matrix has the highest glass transition temperature and the best normalized leaching rate of Ce when doped with 15.79wt% B2O3.更多还原