Development of a dynamic-mesh porosity transport model for multi-dimensional fuel performance codes

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Edoardo Luciano Brunetto , Carlo Fiorina , Andreas Pautz , Sander van Til , Fitriana Nindiyasari , Alexander Fedorov , Alessandro Scolaro
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引用次数: 0

Abstract

The porosity redistribution within nuclear fuel pellets exposed to high power ratings plays a critical role in the thermo-mechanical behavior of fast reactor fuel. Traditional fuel performance codes predict porosity migration through advection-dominated transport equations often assuming a fixed geometry, and limiting their accuracy in asymmetric conditions. A novel dynamic-mesh porosity migration model has been developed to address these limitations. For verification and demonstration purposes, the model has been implemented in OFFBEAT, a multidimensional OpenFOAM-based fuel performance code. The solver dynamically adjusts the fuel pellet geometry to model the evolution of the central hole caused by pore migration. Mesh quality is preserved throughout the simulation by means dynamic-mesh algorithms involving the resolution of a mesh-motion equation to diffuse the displacement imposed at the mesh boundaries to all the domain points. The methodology incorporates modifications to the traditional porosity transport equation, correcting the advective fluxes in the governing equations to account for mesh points movement. A simple mechanistic model to determine the hole expansion velocity as a function of the local porosity, pore velocity and inner fuel radius is proposed. The model's parameters are calibrated using open literature experimental data, demonstrating the solver capability to predict central void diameters within acceptable discrepancy. The dynamic-mesh solver shows good accuracy in predicting off-centered hole formations and aligns well with post-irradiation examination data. This new approach preserves the foundational principles of existing porosity migration models while offering enhanced flexibility and accuracy in asymmetric heat transfer scenarios.
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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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