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高放废液中~(126)Sn的放化分析

高放废液中~(126)Sn的放化分析[J]. 原子能科学技术, 1993, 27(6): 549-549. DOI: 10.7538/yzk.1993.27.06.0549
引用本文: 高放废液中~(126)Sn的放化分析[J]. 原子能科学技术, 1993, 27(6): 549-549. DOI: 10.7538/yzk.1993.27.06.0549
ZHANG SHENGDONG;GUO JINGRU;CUI ANZHI;LIU DAMING;LI DAMING China Institute of Atomic Energy, P. O. Box 275(26), Beijing, 102413. RADIOCHEMICAL ANALYSIS OF ~(126)Sn IN HIGH-LEVEL LIQUID WASTE[J]. Atomic Energy Science and Technology, 1993, 27(6): 549-549. DOI: 10.7538/yzk.1993.27.06.0549
Citation: ZHANG SHENGDONG;GUO JINGRU;CUI ANZHI;LIU DAMING;LI DAMING China Institute of Atomic Energy, P. O. Box 275(26), Beijing, 102413. RADIOCHEMICAL ANALYSIS OF ~(126)Sn IN HIGH-LEVEL LIQUID WASTE[J]. Atomic Energy Science and Technology, 1993, 27(6): 549-549. DOI: 10.7538/yzk.1993.27.06.0549

高放废液中~(126)Sn的放化分析

  • 摘要: 以甲基异丁基酮(MIBK)萃取为主要步骤,放化分离高放废液中的~(126)Sn。全流程化学回收率约为60%。以SnO_2形式制成测量源,用HPGe γ谱仪测取γ谱图,由~(126)Sn的子体特征γ能峰面积,经化学回收率、探测效率校正后,计算得到高放废液中~(126)Sn的含量为371±29 Bq/ml。~(126)Sn的放射性活度约为高放废液总活度的4×10~(-7)。

     

    Abstract: In order to measure the content of ~(126)Sn in high-level liquid waste, a method of determining~(126)Sn is developed. The principal step of method is extraction with methyl iso-butyl ketone(MIBK). The recovery of Sn is approximately 60%, and analysis can be performed in about 3hours. ~(126)Sn is separated from high--level liquid waste and measured by HPGe γ spectrometersystem. The detected radioactivity of ~(126)Sn in high-level liquid waste is 371±29 Bq/ml, the ratioof which to the total radioactivity of high--level liquid waste is about 4×10~(-7).

     

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出版历程
  • 收稿日期:  1992-10-11
  • 刊出日期:  1993-11-19

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