1. 上海交通大学核科学与工程学院
2. 中国船舶及海洋工程设计研究院
3. 复旦大学现代物理研究所
纸质出版:2026
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吴淳熙, 李翰卿, 张婷婷, 等. 六棱柱基体TRISO基燃料导热数值研究[J]. 核科学与工程, 2026,46(2):446-456.
吴淳熙, 李翰卿, 张婷婷, et al. 六棱柱基体TRISO基燃料导热数值研究[J]. 2026, 46(2): 446-456.
吴淳熙, 李翰卿, 张婷婷, 等. 六棱柱基体TRISO基燃料导热数值研究[J]. 核科学与工程, 2026,46(2):446-456. DOI: 10.20190/j.cnki.02580918.202602026.
吴淳熙, 李翰卿, 张婷婷, et al. 六棱柱基体TRISO基燃料导热数值研究[J]. 2026, 46(2): 446-456. DOI: 10.20190/j.cnki.02580918.202602026.
在反应堆运行过程中,随机弥散于芯块中的TRISO燃料颗粒的尺寸会因燃耗的增加而发生变化。为揭示在六棱柱基体中TRISO燃料颗粒位置和尺寸随机分布对燃料芯块温度分布的影响,同时建立相关导热模型,对位置随机分布,尺寸服从正态分布或均匀分布的燃料颗粒通过相关算法进行生成,并使用ANSYS软件对六棱柱基体进行建模,通过数值模拟获得了燃料芯块三维温度场分布。本文对燃料芯块的最高温度进行了统计分析,同时依赖已建立的“双区”导热模型和不同几何简化方法对燃料芯块中心横截面的径向温度分布进行了预测,并与现有的多种等效导热模型进行了对比。研究发现,燃料芯块最高温度近似服从正态分布规律,“双区”模型能够在同时考虑颗粒尺寸和位置随机分布的情况下保守地对六棱柱形TRISO基燃料的最高温度进行预测。
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The University of New Mexico, 1 University of New Mexico, Albuquerque, NM 87131, USA,The University of New Mexico, 1 University of New Mexico, Albuquerque, NM 87131, USA,The University of New Mexico, 1 University of New Mexico, Albuquerque, NM 87131, USA,The University of New Mexico, 1 University of New Mexico, Albuquerque, NM 87131, USA.Conceptual design of a freeze-tolerant Direct Reactor Auxiliary Cooling System for Fluoride-salt-cooled High-temperature Reactors[J].Nuclear Engineering and Design,2018.
Matteo Minelli,Ferruccio Doghieri,Kyriaki G. Papadokostaki,John H. Petropoulos.A fundamental study of the extent of meaningful application of Maxwell's and Wiener's equations to the permeability of binary composite materials. Part I: A numerical computation approach[J].Chemical Engineering Science,2013.
Klaudio Bari,Sohaib Z. Khan,Tristan Lowe,Johar K. Farooqi.Measurement of thermal diffusivity for alumina borosilicate glass bearing TRISO fuel particles: Experiment and modelling correlation[J].Journal of Materials Science,2013.
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