γ能谱法在快堆新燃料^(235)U富集度核实测量中的应用  

Application of γ-NDA Method in Fast Neutron Reactor Fresh Fuel's Uranium Enrichment Measurement

作　　者：何丽霞[1] 蒙延泰[1] 邵婕文[1] 郜强[1] 

机构地区：[1]中国原子能科学研究院核保障技术重点实验室,北京102413

出　　处：《同位素》2008年第1期61-64,共4页Journal of Isotopes

摘　　要：采用无损分析方法中最常用的γ能谱法及专用分析软件PC/FRAM核实了中国原子能科学研究院实验快堆新燃料中235U富集度的标称值。从实验角度出发,首先对系统进行了标样测量验证,在新燃料库房任取8根新燃料单棒,分段取点测量,计算得8根单棒的235U富集度与标称值偏差绝大部分在3%以内。以上结果提示,γ能谱法用于快堆新燃料235U富集度测量的方法可取,在核燃料设施加工与核电站进行新燃料组件交接方面可以推广应用。γ-spectrometry in non-destructive assay field and special PC/FRAM code were used to verify fresh fuel rods＇ ^235U enrichment declared value, which will be used in Chinese experiment fast neutron reactor. The experiment required system should be validated by u- ranium standards. Different plots on 8 fresh fuel rods were measured. The results show that most of the ^235U enrichment deviation between measured value and declared are less than 3%. So, it can be concluded that γ-spectrometry is efficient in verifying ^235U enrichment in fuel rods which will be used in reactors; and this method should be widely used in fuel transfers between nuclear power plant and fresh fuel manufactories.

关 键 词：快堆新燃料组件 ^235U富集度 Γ能谱法 

分 类 号：TL271[核科学技术—核燃料循环与材料] TL817.2