微型中子源堆低浓化堆芯的探讨  

THE PHYSICAL SCHEME OF LOW ENRICHMENT CORE OF MINIATURE NEUTRON SOURCE REACTOR

作　　者：李德江[1] 田和春[1] 

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所

出　　处：《原子能科学技术》1997年第5期408-412,共5页Atomic Energy Science and Technology

摘　　要：通过对２３５Ｕ富集度为１９．９％的ＵＯ２和Ｕ３Ｓｉ２－Ａｌ的弥散体２种燃料进行物理计算，从中筛选出了优化的堆芯方案，并对其静态物理参数，诸如有效倍增因子、绝对中子通量密度、上铍反射层反应性价值、反应性温度系数、控制棒价值等进行了计算。The scheme of low enrichment fuel core for miniature neutron source reactor is discussed in the paper.From a great deal of physics calculations for 19 9% enrichment UO 2 fuel and 19 9% enrichment U 3Si 2 Al dispersion fuel used in reactor cores, an optimization scheme is chosen. Some parameters for this reactor are calculated such as effective multiplication factor,absolute neutron flux density,up beryllium reflector worth, temperature coefficient of reactivity and control rod worth.

关 键 词：微形堆 低浓化 堆芯优化 中子源堆 铀燃料 

分 类 号：TL411.7[核科学技术—核技术及应用]