In-pile heat conduction model of the dispersion nuclear fuel plate with particle agglomeration. Part I: Numerical method and analysis of influencing factors
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Abstract
Within a dispersion nuclear fuel plate element, a substantial amount of fuel particles distribute non-uniformly and exhibit the local agglomeration phenomenon, resulting in a reduction in the thermal transfer efficiency. The main aim of this study is to develop the numerical calculation method for the effective thermal conductivity of the dispersion nuclear fuel plate along the thickness direction under an unique in-pile thermal transfer pattern, and determine the influencing mechanisms of key parameters, in particular the particle agglomeration. A modified analytical model, incorporating the influence of particle agglomeration, was constructed based on the equivalent transformation approach for calculating the effective thermal conductivity. Furthermore, according to the in-pile heat conduction mode of the dispersion fuel meat, an internal heat source model was developed and numerically implemented in FEM simulations. Extensive analyses were conducted to investigate the influencing mechanisms of crucial microstructural parameters. Simulation results suggest that the extent of particle agglomeration shows an apparent power law relation with the effective thermal conductivity. The in-pile thermal transfer pattern substantially impairs the inherent thermal conductivity across the meticulously refined dispersion meat structure. This study lays a foundation for optimizing the design of dispersion nuclear fuel plate and enhancing the safety of reactor cores.
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.