| 乏燃料废包壳残留物质核素分析计算 |
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| 引用本文： | 夏兆东,吕牛,成昱廷,郑继业.乏燃料废包壳残留物质核素分析计算[J].原子能科学技术,2019,53(4):689-694. |
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| 作者姓名： | 夏兆东 吕牛 成昱廷 郑继业 |
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| 作者单位： | 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 |
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| 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244Cm含量、总Pu含量及244Cm/Pu比等主要参数随燃耗及冷却时间的变化。计算结果表明，244Cm含量、总Pu含量及244Cm/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。
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| 关 键 词： | 乏燃料废包壳 核素分析 244Cm" target="_blank">244Cm')">244Cm 总Pu含量 |
Analysis of Nuclide Composition of Spent Fuel Waste Cladding Residue |
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| XIA Zhaodong,LYU Niu,CHENG Yuting,ZHENG Jiye.Analysis of Nuclide Composition of Spent Fuel Waste Cladding Residue[J].Atomic Energy Science and Technology,2019,53(4):689-694. |
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| Authors: | XIA Zhaodong LYU Niu CHENG Yuting ZHENG Jiye |
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| Affiliation: | 1.China Institute of Atomic Energy, P. O. Box 275-45, Beijing 102413, China; 2.Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China |
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| Abstract: | 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 244Cm content, total Pu content and 244Cm/Pu ratio with burnup and cooling time was calculated by SCALE code. The results show that the variation of 244Cm content, total Pu content and 244Cm/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. |
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| Keywords: | spent fuel waste cladding analysis of nuclide 244Cm total Pu content |
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