乏燃料后处理溶液中U、Pu的^(57)Co源激发K-XRF分析  

57 Co SOURCE EXCITED K XRF ANALYSIS OF U AND Pu CONCENTRATIONS IN PWR SPENT FUEL REPROCESSING SOLUTION

作　　者：金立云[1] 黄清良[1] 袁慧[1] 李云[1] 祝亮[1] 王里玉[1] 丁锡祥 刘聪 

机构地区：[1]中国原子能科学研究院放射化学研究所

出　　处：《核化学与放射化学》1998年第3期138-145,共8页Journal of Nuclear and Radiochemistry

摘　　要：自制一套５７Ｃｏ源激发Ｋ系Ｘ射线荧光（Ｋ－ＸＲＦ）分析系统。用５７Ｃｏ的１２２ｋｅＶγ射线激发工艺溶液中Ｕ、Ｐｕ的Ｋ系Ｘ射线荧光，用ＨＰＧｅ探测器－多道微机分析系统进行测量，并以１２２ｋｅＶγ射线康普顿散射线为内标，建立强度比－浓度校正曲线，快速无损地测定ＰＷＲ乏燃料后处理工艺溶液中Ｕ、Ｐｕ浓度。测定范围为０．５—２００ｇ／Ｌ，精密度为５．０％—１．５％。方法适于ＰＷＲ乏燃料后处理工艺中Ｕ、Ｐｕ浓度的快速控制分析或在线分析。在同时应用５７Ｃｏ透射源的情况下，精密度达０．５％，方法适于核燃料衡算分析。An analysis system composed of 57 Co source excited K XRF apparatus and HPGe detector multichannel computer is developed.According to requirements of control analysis of PWR spent fuel reprocessing process,a nondestructive,rapid analysis method for U and Pu concentrations has been investigated.The range of determination is 0.5-200 g/L with precision ( s r) of 5.0%-1.5%.The effect of solution medium composition on determination of concentrations of U and Pu can be ignored.The method is well suited to control or in line analyze concentrations of U and Pu in PWR spent fuel reprocessing process.If 57 Co transmission source is applied simultaneously,the method can also be suited to material accounting of U and Pu for nuclear safeguards.

关 键 词：乏燃料后处理 PWR 铀 镨 K-XRF 核工艺控制分析 

分 类 号：TL241[核科学技术—核燃料循环与材料] TL271.5