An application of the DEM-FFT method to predict the thermal conductivity of high burnup fragmented fuel

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Fabien Bernachy-Barbe, Jean-Mathieu Vanson, Marc Josien
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引用次数: 0

Abstract

Understanding Fuel Fragmentation, Relocation and Dispersal (FFRD) phenomena is a major item to predict the behavior of fuel rods in the event of a Pressurized Water Reactor loss-of-coolant hypothetical scenario. In order to introduce an effective medium for fragmented fuel that could be used in fuel performance codes, the heat transfer properties of UO2 granular beds in He-Kr-Xe gas mixes was studied numerically. The Discrete Element Method was first used to compute the spatial arrangement of fragments only submitted to gravity with a representative granulometric distribution. These generated geometries were then transformed into a 3D grid (voxelized) to perform numerical homogenization and compute their effective properties using a Fast Fourier Transform solver for heat transfer. Different hypotheses were made in the voxelation process about the treatment of gas-solid and solid-solid interfaces, which in turn provided different estimates of the effective properties. Due to limits on the discretization and extended particle size distributions, a two-scale scheme was introduced and numerically tested against direct computations. For several granular beds, computed thermal conductivities were compared to analytical models for granular materials. Some heat transfer properties of fragmented fuel at several burnups were then computed, taking into account approximations for Knudsen and radiation size effects.
应用 DEM-FFT 方法预测高燃耗碎片燃料的热导率
了解燃料碎裂、移位和分散(FFRD)现象是预测压水堆失去冷却剂假想情况下燃料棒行为的一个重要项目。为了引入一种可用于燃料性能代码的有效碎裂燃料介质,对 He-Kr-Xe 气体混合物中的二氧化铀颗粒床的传热特性进行了数值研究。首先使用离散元素法计算了仅受重力作用的碎片的空间排列,这些碎片具有代表性的粒度分布。然后将这些生成的几何图形转换为三维网格(体素化),以执行数值均质化,并使用快速傅里叶变换热传递求解器计算其有效特性。在象素化过程中,对气固界面和固固界面的处理提出了不同的假设,这反过来又提供了对有效特性的不同估计。由于离散化和扩展粒度分布的限制,引入了双尺度方案,并对直接计算进行了数值测试。对于几个颗粒床,将计算得出的热导率与颗粒材料的分析模型进行了比较。然后,考虑到努森效应和辐射尺寸效应的近似值,计算了几种燃烧速度下碎片燃料的一些传热特性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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