乏燃料废包壳残留物质核素分析计算  

Analysis of Nuclide Composition of Spent Fuel Waste Cladding Residue

作　　者：夏兆东[1] 吕牛[1] 成昱廷 郑继业[2] XIA Zhaodong;LYU Niu;CHENG Yuting;ZHENG Jiye(China Institute of Atomic Energy,P.O.Box 275-45,Beijing 102413,China;Nuclear and Radiation Safety Center,Ministry of Environmental Protection,Beijing 100082,China)

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413 [2]环境保护部核与辐射安全中心,北京100082

出　　处：《原子能科学技术》2019年第4期689-694,共6页Atomic Energy Science and Technology

摘　　要：为分析计算乏燃料废包壳残留物质的核素含量,以M310型核电机组及燃料组件为分析对象,建立了乏燃料废包壳残留物质核素含量分层计算模型,用SCALE程序计算分析了^(244)Cm含量、总Pu含量及^(244)Cm/Pu比等主要参数随燃耗及冷却时间的变化。计算结果表明,^(244)Cm含量、总Pu含量及^(244)Cm/Pu比随燃耗及冷却时间的变化均可用三阶多项式拟合。本文工作为废包壳残留物质非破坏性测量方法研究提供了数据支持。In order to analyze the nuclide content of spent fuel waste cladding residue,a multilayer calculation model was established for M310 nuclear power plant and fuel assembly.The variation of 244 Cm content,total Pu content and 244 Cm/Pu ratio with burnup and cooling time was calculated by SCALE code.The results show that the variation of 244 Cm content,total Pu content and 244 Cm/Pu ratio with burnup and cooling time can be fitted by third-order polynomial.This study provides data support for non-destructive analysis method of waste cladding residue.

关 键 词：乏燃料废包壳 核素分析 244Cm 总Pu含量 

分 类 号：TL325[核科学技术—核技术及应用]