Wenwen Zhang , Wenli Guo , Wentao Hao , Ding She , Wei Li
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引用次数: 0
Abstract
A representative volume element (RVE) model was developed to investigate the thermo-mechanical behavior of U3Si2/Al dispersion fuel under irradiation. The study focused on the evolution of thermal expansion, elastic properties, creep, and irradiation-induced swelling across varying irradiation conditions. RVE models with different uranium densities were constructed using Voronoi tessellation to approximate the irregular geometry of fuel particles. A phase-field approach was employed to simulate the growth of the interaction layer. Coupled with the finite element method (FEM), a series of detailed simulations were conducted. The simulations revealed that increasing interaction layer thickness (from 0 μm to 20 μm) significantly reduces the thermal expansion coefficient by up to 28 % while increasing stiffness. Higher fission density and fuel particle volume fraction lead to greater swelling strain. The effect of interaction layer thickness on equivalent swelling strain exhibits a dual behavior. The creep behavior is affected by both the interaction layer volume fraction and the applied stress, and can be effectively described by a polynomial-based constitutive model. Compared to traditional homogenization methods, the RVE approach offers improved accuracy in capturing the effects of microstructural heterogeneity on macroscopic fuel performance. These results demonstrate the model applicability for evaluating and optimizing dispersion fuel behavior under irradiation.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.