钍铀自持循环物理热工特性研究  

Physics and thermal-hydraulic research on U-Th self-sustaining cycle

作　　者：侯周森[1] 周涛[1] 陈娟[1] 罗峰[1] 程万旭[1] 

机构地区：[1]华北电力大学核热工安全与标准化研究所,北京102206

出　　处：《核技术》2012年第10期795-800,共6页Nuclear Techniques

基　　金：国家重点基础研究发展计划(2007CB209800)资助;中国科学院战略先导科技专项(XDA03040000)资助

摘　　要：采用CANFLEX43型燃料棒为驱动燃料棒,基于燃料棒的富集度不同,设计了三种驱动方案。通过Dragon程序及建立的热工模型,对三种方案的燃料棒束栅元物理热工特性及冷却剂平均温度进行敏感性分析研究。结果表明:233U富集度为1.4%的驱动方案下换料燃耗为16 MWd/kg,233U增量为5.9872 g,燃料包壳表面最高温度371oC,燃料芯块中心温度1830oC;单个通道冷却剂最大流量为25.4 kg/s,均能很好满足钍铀自持循环物理热工特性的要求。The realization of thorium uranium self-sustaining cycle and meet its physics and thermal-hydraulic requirements, it is an important question in the thorium uranium fuel recycling. （Th-U）O2 CANFLEX43 fuel bundle includes two types of fuel elements, the ThO2 elements in the inner two rings and the slightly enriched uranium （SEU） elements in the outer two rings as driving fuel rods. The three driving schemes are introduced in this paper based on different enrichment of drive fuel rods. The neutronic physics calculation by Dragon Program and the thermal-hydraulic analysis are executed. The results are as follows： at 1.4% enrichment of 233U, the fuel consumption is 16 MWd/kg, the 233U production is 5.9872 g, the highest surface temperature of the fuel rod cladding is 371℃, temperature in the fuel rod center is 1830℃, and the maximum flow in the single channel is 25.4 kg/s. These parameters meet the requirements of thorium uranium self-sustaining cycle.

关 键 词：钍铀自持循环 富集度 微浓缩铀元件 ThO2 燃耗 

分 类 号：TL249[核科学技术—核燃料循环与材料]