Crystal plasticity model for UO2: Introduction of the dislocation climbing and coupling with the thermally activated gliding

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
S. ElBez , M. Garajeu , B. Michel
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Abstract

Modelling of viscoplastic behaviour of UO2 nuclear fuel at high temperature is of major interest to analyze the risk of cladding failure in power transient condition where pellet to cladding mechanical interaction occurs. In this study, we investigate the impact of dislocation climbing on the viscoplastic behaviour of UO2 single crystal at high temperature where climbing mechanism is activated by vacancy diffusion. The modelling framework is that of an existing crystal plasticity law devoted to thermally activated gliding for lower temperatures. The constitutive equation of the crystal plasticity model are modified in order to add dislocation interaction hardening and stored dislocation recovery. The latter is assessed with dynamic recovery induced by cross slip and static recovery induced by dislocation climbing. A phenomenological model is proposed to compute the dislocation climbing velocity and the associated dislocation density recovery rate. The dislocation gliding velocity law is also improved with a physically based formulation introducing the activation energy for a double kink mechanism. The complete model, for low and high temperatures, is built with a harmonic coupling function enabling a more physically based formulation of the constitutive equations devoted to each mechanism. An implicit numerical implementation of the resulting model is proposed with a finite strain formulation in the framework of the MFront open source tool. A first validation of the complete model has been done with experiment/simulation comparisons for single crystal creep compression tests. In this first step, the validation is limited to orientations where only the modes 1 and 2 (soft and hard slip modes) are suspected of having a major contribution to the viscoplastic behaviour. Thanks to the contribution of dislocation gliding, interaction and climbing we can explain the evolution of the compression flow stress as a function of the temperature from 800 °C to 1600 °C in good agreement with experimental results. The physically based formulation gives also a justification of the temperature dependency of the apparent thermal activation energy and of the strain rate sensitivity.
UO2晶体塑性模型:引入位错爬升与热激活滑动耦合
模拟UO2核燃料在高温下的粘塑性行为,对于分析在动力瞬态条件下包层失效的风险具有重要意义。在这项研究中,我们研究了位错爬升对UO2单晶在高温下粘塑性行为的影响,其中爬升机制是由空位扩散激活的。建模框架是现有的晶体塑性定律,致力于低温下的热激活滑动。修正了晶体塑性模型的本构方程,加入位错相互作用硬化和存储位错恢复。后者由交叉滑移引起的动态恢复和位错爬升引起的静态恢复来评估。提出了一种计算位错爬升速度和相应的位错密度恢复速率的唯象模型。通过引入双扭结机制的活化能,改进了位错滑动速度定律。完整的低温和高温模型是用谐波耦合函数建立的,使得每个机构的本构方程的表述更加基于物理。在MFront开源工具的框架下,用有限应变公式提出了结果模型的隐式数值实现。通过单晶蠕变压缩试验的实验/模拟比较,对完整模型进行了首次验证。在第一步中,验证仅限于方向,其中只有模式1和2(软滑移模式和硬滑移模式)被怀疑对粘塑性行为有主要贡献。由于位错滑动、相互作用和爬升的贡献,我们可以解释压缩流动应力随温度从800°C到1600°C的变化规律,与实验结果吻合较好。基于物理的公式也证明了表观热活化能和应变率敏感性的温度依赖性。
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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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