多维燃料性能代码动态网格孔隙输运模型的建立

IF 3.3 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-04-01 Epub Date: 2025-02-28 DOI:10.1016/j.jnucmat.2025.155717
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

摘要

高额定功率下核燃料团块内部孔隙度的重新分布对快堆燃料的热力学行为起着至关重要的作用。传统的燃料性能代码通过平流主导的输运方程来预测孔隙度迁移,通常假设一个固定的几何形状,这限制了它们在不对称条件下的准确性。一种新的动态网格孔隙度迁移模型已经被开发出来以解决这些限制。为了验证和演示,该模型已经在OFFBEAT中实现,OFFBEAT是一个基于openfoam的多维燃料性能代码。求解器通过动态调整燃料球团的几何形状来模拟孔隙迁移引起的中心孔的演化。在整个模拟过程中,通过动态网格算法(涉及网格运动方程的分辨率)将网格边界处施加的位移扩散到所有域点,从而保持网格质量。该方法结合了对传统孔隙度输运方程的修正,修正了控制方程中的对流通量,以考虑网格点的运动。提出了一个简单的机制模型来确定孔洞膨胀速度作为局部孔隙率、孔隙速度和内部燃料半径的函数。模型的参数使用公开文献实验数据进行校准,证明求解器能够在可接受的误差范围内预测中心空洞直径。动态网格求解器在预测偏心地层方面具有较高的精度,并且与辐照后的检测数据吻合良好。这种新方法保留了现有孔隙度迁移模型的基本原理,同时在非对称传热情况下提供了更高的灵活性和准确性。
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Development of a dynamic-mesh porosity transport model for multi-dimensional fuel performance codes
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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