In-pile heat conduction model of the dispersion nuclear fuel plate with particle agglomeration. Part II: Predicting the effective thermal conductivity under the in-pile thermal transfer pattern based on a deep neural network
Yingxuan Dong , Xicheng Cao , Xingming Peng , Junnan Lv , Qun Li
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引用次数: 0
Abstract
In-pile dispersion nuclear fuel plate elements incorporate multiple internal heat sources and evolving interaction layers. The effective thermal conductivity of this complex heat conduction structure exhibits multivariate and highly nonlinear characteristics, requiring accurate prediction by combining numerical methods and machine learning techniques. This study developed an automated high-throughput workflow to rapidly simulate massive number of dispersion meat models with diverse microstructures, and further established the machine learning database for predicting the effective thermal conductivity. Influences of internal heat sources within fuel particles, the particle agglomeration and interaction layers were considered simultaneously in modeling. Through utilizing the database constructed by high-throughput computing, the deep neural network was successfully applied to accurately forecast the effective thermal conductivity of the in-pile dispersion meat. Furthermore, comparisons of the predictive performances determined by different distance-based point pattern analysis methods indicated that the radial distribution function (g(r)) served as the most effective approach for characterizing spatial discreteness in predicting the effective thermal conductivity. This work demonstrates that thermal conductivity of ceramic dispersion nuclear fuel plate elements can be enhanced via optimizing the critical microstructural features.
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.