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)。
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).
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
1993年第6期549-552,共4页
Atomic Energy Science and Technology
