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乏燃料后处理溶液中U、Pu的57Co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

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【作者】 金立云黄清良袁慧李云祝亮王里玉丁锡祥刘聪

【Author】 Jin Liyun Huang Qingliang Yuan Hui Li Yun Zhu Liang Wang Liyu Ding Xixiang Liu Chong(China Institute of Atomic Energy,P.O.Box275(88), Beijing 102413)

【机构】 中国原子能科学研究院放射化学研究所

【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。

【Abstract】 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.

  • 【文献出处】 核化学与放射化学 ,JOURNAL OF NUCLEAR AND RADIOCHEMISTRY , 编辑部邮箱 ,1998年03期
  • 【分类号】TL24,O657.34
  • 【被引频次】5
  • 【下载频次】103
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