中子源驱动的融盐燃料次临界堆的概念研究  

Conceptual Study of the Subcritical Molten Salt Reactor Driven by a Neutron Source

作　　者：刘成安[1] 伍钧[1] 

机构地区：[1]北京应用物理与计算数学研究所

出　　处：《高技术通讯》1998年第2期51-54,共4页Chinese High Technology Letters

摘　　要：对中子源驱动的次临界融盐堆作了中子学及燃耗特性的分析研究。这种堆型具有充分利用２３８Ｕ、２３２Ｔｈ，防止核武器扩散及生产氚的优点。值得对其作进一步开发研究。In this paper, proceed from the steady development of nuclear energy and national security, the subcritical molten salt reactor driven by neutron source has being studied, the characteristics of and burn up have been calculated and analyzed. This kind of the reactor bombines with the advantages of making fuel using 238 U、 232 Th, producing tritium, preventing nuclear proliferation and warrants has being studied and developed.

关 键 词：融盐氟化物 中子驱动 次临界包层 核能源 

分 类 号：TL281[核科学技术—核燃料循环与材料]