首页> 外文会议>9th International Conference on Environmental Remediation and Radioactive Waste Management >DIFFERENT PATHWAYS OF SECONDARY PHASE FORMATION INDUCED BY COLLOIDAL AND DISSOLVED SILICA DURING THE DISSOLUTION OF UO_2 NUCLEAR FUEL IN LEACHING TESTS
【24h】

DIFFERENT PATHWAYS OF SECONDARY PHASE FORMATION INDUCED BY COLLOIDAL AND DISSOLVED SILICA DURING THE DISSOLUTION OF UO_2 NUCLEAR FUEL IN LEACHING TESTS

机译:UO_2核燃料溶解过程中胶体和溶解二氧化硅引起的二次相形成的不同途径。

获取原文

摘要

We investigated the different dissolution behaviour of UO_2 nuclear fuel material in waters containing silica in two different physical and chemical forms (dissolved ions and as SiO_2 colloids, respectively) at elevated temperatures (95°C in autoclaves). It was investigated if SiO_2 colloids can act as carrier material for U ions during a interface geochemical dissolution process, a process that might possibly enhance the mobilization of uranium. Herefore, leaching / dissolution tests were conducted in batch reactors, using both dissolved Si (sodium metasilicate solution), as well as synthetic SiO_2 colloids (100 nm diameter). Solid materials were examined with scanning electron microscopy (SEM-EDX) after the tests and ICP-OES was used for analysis of concentrations of U and Si in solutions. Thermodynamic calculations were applied for modelling the surface charges of the solid materials. Results show that a treatment with colloidal SiO_2 has different effects on the surfaces than a leaching in dissolved silicate solutions. In the presence of colloids, well-crystallized secondary phases containing U and Si (most obviously uranyl silicates) were found on the surfaces, which were attacked by the treatment. This was not the case when dissolved Si was used. SiO_2 colloids were partly found to remain on the surfaces after 1000 h at 95°C. Dissolved U concentrations decreased with increasing Si content in the systems, especially so when colloidal Si was used. Ultrafiltration showed that the greatest part of the dissolved U was associated with Si colloids. A surface charge model suggests that the different effects are due to the development of electrostatic interactions between the UO_2 and SiO_2 surfaces.
机译:我们研究了在高温(高压灭菌器中为95°C)下,UO_2核燃料材料在含有两种不同物理和化学形式(分别为溶解离子和SiO_2胶体)的二氧化硅的水中的不同溶解行为。研究了SiO_2胶体是否可以在界面地球化学溶解过程中充当U离子的载体材料,该过程可能会增强铀的迁移。因此,使用溶解的Si(偏硅酸钠溶液)以及合成的SiO_2胶体(直径100 nm)在分批反应器中进行浸出/溶解测试。测试后,用扫描电子显微镜(SEM-EDX)检查固体材料,并使用ICP-OES分析溶液中U和Si的浓度。热力学计算被用于模拟固体材料的表面电荷。结果表明,与在溶解的硅酸盐溶液中浸出相比,用胶体SiO_2处理对表面的影响不同。在胶体的存在下,在表面上发现了含有U和Si(最明显的是铀酰硅酸铀)的结晶良好的第二相,这些相受到了处理的攻击。当使用溶解的Si时不是这种情况。 SiO_2胶体在95°C下放置1000小时后部分残留在表面上。溶解的U浓度随系统中Si含量的增加而降低,尤其是当使用胶体Si时。超滤表明,溶解的U的大部分与Si胶体有关。表面电荷模型表明,不同的作用是由于UO_2和SiO_2表面之间静电相互作用的发展所致。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号