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中文核心期刊

自辐照钚合金力学本构模拟研究

Mechanical Constitutive Modeling of Self-Irradiated Plutonium Alloys

  • 摘要: 为了预测钚合金自辐照老化后的宏观力学行为, 并准确描述变形过程当中的微观结构的演化特性, 本文发展了基于位错理论的晶体塑性本构模型. 模型不仅考虑了滑移系激活、位错增殖和湮灭、辐照缺陷演化等微观机制, 还构建了位错与辐照缺陷演化的耦合关系, 提出缺陷数密度率与体积分数的动态演化方程, 建立了自辐照钚合金从微观物理机制到宏观力学行为的定量关联. 在此基础上, 将所构建的本构模型与有限元方法相结合, 并通过未老化钚合金拉伸结果标定参数, 实现了对不同老化时间、温度及应变率工况下钚合金应力-应变曲线的模拟预测. 结果表明: 因位错对辐照缺陷的吸收效应, 老化钚合金屈服后表现出先软化再硬化的现象, 同时伴随变形局域化特征; 加速辐照条件下, 钚合金从屈服到硬化则呈现平滑过渡特征, 揭示了位错与缺陷共同演化对其力学性能的调控机制. 本工作为钚合金构件的长期服役安全性评估提供可靠的理论支撑与计算工具.

     

    Abstract: A dislocation-based crystal plasticity constitutive model is developed to predict the microstructural evolution and macroscopic mechanical behavior of self-irradiated, aged plutonium alloys. The model incorporates fundamental microscopic mechanisms, including slip system activation, dislocation multiplication and annihilation, and irradiation-induced defect evolution. Furthermore, it accounts for the interaction between dislocations and radiation defects through a proposed hardening and evolution rate theory. Implemented within a finite element method (FEM) framework, the model parameters are calibrated against experimental tensile data for unaged plutonium alloys. The model is subsequently applied to predict the stress-strain response of single-crystal plutonium alloys across various aging times, temperatures, and strain rates. Results indicate that aged plutonium alloys exhibit a distinct softening-then-hardening post-yielding behavior due to dislocation-defect interactions, which is accompanied by plastic deformation localization. For cases of accelerated irradiation conditions, the alloys present a smooth elastic-plastic transition, revealing the concurrent effects of defect generation and dislocation-defect interaction. This work provides a theoretical foundation and computational tools for the long-term service safety assessment of plutonium alloy components.

     

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