研究堆乏燃料组件中^(235)U含量和燃耗的测定  

Measurement of ^(235)U Mass and Burnup in Fuel Assembly in Research Reactors

作　　者：李润东[1] A.V.Bushyev A.F.Korin 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900 [2]莫斯科工程物理学院

出　　处：《核动力工程》2009年第1期56-59,共4页Nuclear Power Engineering

摘　　要：介绍了利用乏燃料组件再次辐照和γ谱对比法确定研究堆中235U含量及其燃耗成分的方法,描述了在俄罗斯IRT-MIFI堆上对IRT-3M燃料组件进行分析测定的条件装置和实验过程,给出了相应的实验结果和不确定度评价。结果表明,用该方法分析高浓铀核燃料组件中235U的含量可以得到小于2%的不确定度。The method for measurement of ^235U mass and bumup in fuel assembly in research reactors with comparison γ-Spectrum after irradiation is introduced in this paper. It also described the equipment, condition and experimental process of measurement IRT-3M fuel assembly in reactor IRT-MIFI in Russia, and presented relevant experiment result and its estimate of uncertainty. The result indicates the probability to obtain data of ^235U mass in concentrated fuel assembly with uncertainty less than 2% by application of this method.

关 键 词：辐照 γ谱对比 燃料组件 燃耗 

分 类 号：TL327[核科学技术—核技术及应用]