球形燃料元件中包覆燃料颗粒的化学分析  

Chemical analysis of coated particles in spherical fuel element

作　　者：郑文革[1] 倪晓军[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《核技术》2001年第3期211-215,共5页Nuclear Techniques

基　　金：86 3重大项目! (86 3- 6 14- 0 2 )

摘　　要：报道了高温气冷堆球形燃料元件中包覆燃料颗粒的表面铀沾污、自由铀含量及包覆燃料颗粒的装铀量等性能指标的测试方法、范围及测量误差。利用激光荧光法测量并计算了包覆燃料颗粒中的自由铀含量及表面铀沾污 ,利用电位滴定法测量了包覆燃料颗粒的装铀量。结果表明 ,经 4层连续包覆的包覆燃料颗粒的质量符合并满足高温气冷堆球形燃料元件对包覆燃料颗粒的设计要求。The free uranium content (the ratio of free uranium which is not entirely coated with SiC layer in coated fuel particles to total uranium in coated fuel particles) and the uranium content were studied and determined by laser-induced fluorimetric method and titration with a potentiometer. The sample was burned in air first, then immersed and refluxed in nitric acid to separate the free uranium with coated fuel particles to the nitric acid solution. The uranium content in sample solution can be directly measured by laser-induced fluorimetric method, other elements had no interference on the determination of uranium. The method is simpler, faster and more accurate than traditional method in uranium analysis. The method has low measurement error of below 10%, and satisfies the needs of the specifications in the manufacture of coated fuel particles.

关 键 词：激光荧光法 自由铀含量 包覆燃料颗粒 球形燃料元件 化学分析 高温气冷堆 表面铀污染 装铀量 

分 类 号：TL424[核科学技术—核技术及应用] TL271