钍在快堆中的利用及其物理特性研究  

Thorium Utilization and Research on Features in FBR

作　　者：陈仪煜[1] 刚直 赵金坤[1] 喻宏[1] 

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《核电工程与技术》2008年第3期42-48,共7页Nuclear Power Engineering and Technology

摘　　要：本文根据Th—U循环在快堆中的利用特点，应用法国ERANOS软件系统，以600MWe快堆堆芯为例，对钍在快堆中的基本物理特性进行了计算分析研究。对转换区的转换比、比产额、年产量和^232U含量等参数进行了分析比较，结果表明：采用（Pu，U）O2混合燃料作为驱动燃料，易裂变核素的初装量更少，钍在转换区作为可转换材料是比较合适的；^238U在堆芯区增殖^1239Pu，^232Th在增殖层增殖^233U，这样分区装料可以充分发挥各区的中子能谱优势；转换区的比产额和年产量较高，^232U含量较低，有利于降低γ辐射，方便后处理。The features of Th-U fuel cycle in fast neutron spectrum were investigated in this article. The basic physical characteristics in the core of 600MWe fast reactor loaded with Thorium were analyzed with French eode ERANOS. The conversion ratio in blanket, fissile mass produeed per year by per kg Thorium, ^232U coneentration etc., were all analyzed and compared. The results show that, Pu-U dioxides, by which firstly loading fissile nuclide mass were less, were suitable for fuel. With the ^238U conversion to ^239Pu in core, and ^232Th conversion to ^233U in blanket,this sub-area load can sufficiently exert the advantages of different area neutron spectrum, and has a big breeding ratio in blanket, and could increase the production mass per year, and reduce the 232^U concentration, thus reduce the γ radiation.

关 键 词：钍/铀循环 快堆 ERANOS 

分 类 号：O614.42[理学—无机化学] TL433[理学—化学]