A spatially-resolved model of neutron-irradiated tungsten coupling stochastic cluster dynamics and finite deformation plasticity

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-11-19 DOI:10.1016/j.jnucmat.2024.155526
Sabyasachi Chatterjee , Qianran Yu , Yang Li , Kenneth Roche , Jaime Marian , Giacomo Po
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Abstract

Structural materials used in nuclear reactors face severe degradation in mechanical properties, such as hardening and embrittlement. At the microscopic scale, this occurs due to creation and accumulation of irradiation-induced defects and their interaction with system dislocations. Although techniques exist which can model evolution of irradiation defects, for instance kinetic transport theory-based models, their interaction with mechanical deformation of the bulk material has not been investigated extensively. In this work, we demonstrate a novel spatially-resolved multiscale coupling between microscopic irradiation defect evolution, modeled using Stochastic Cluster Dynamics (SCD) and macroscopic mechanical deformation modeled using a finite-deformation plasticity model. SCD is used to determine the statistically averaged defect cluster spacing, dependent on operating conditions such as irradiation dose and temperature. This acts as an initial condition that governs the critical resolved shear stress of dislocation glide in the macroscopic plasticity model. This framework is used to predict mechanical behavior in post-mortem test of irradiated Tungsten samples, which has found its importance as structural material used in nuclear reactors. The results obtained using the coupled approach are in good agreement with experimental data of uniaxial tension tests. The model is able to capture the effect of temperature and irradiation dose on the material hardening. Two methods are proposed to estimate hardness – using Tabor's Law relating uniaxial yield stress to hardness and from flat-punch simulations. The results are in reasonable agreement with hardness data from micro-indentation experiments of irradiated Tungsten samples. The model is also able to reveal microstructural details such as spatial variation in defect density and local stress.
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中子辐照钨随机团簇动力学与有限变形塑性耦合的空间分辨模型
核反应堆中使用的结构材料面临着严重的机械性能退化,如硬化和脆化。在微观尺度上,发生这种情况的原因是辐照诱发缺陷的产生和积累,以及它们与系统位错的相互作用。虽然已有技术可以模拟辐照缺陷的演变,例如基于动力学输运理论的模型,但它们与块体材料的机械变形之间的相互作用尚未得到广泛研究。在这项工作中,我们展示了一种新颖的空间分辨多尺度耦合方法,即利用随机簇动力学(SCD)建模的微观辐照缺陷演化与利用有限变形塑性模型建模的宏观机械变形之间的耦合。随机集群动力学用于确定统计平均缺陷集群间距,该间距取决于辐照剂量和温度等操作条件。在宏观塑性模型中,这一初始条件控制着位错滑行的临界解析剪切应力。该框架用于预测辐照钨样品死后测试中的机械行为,辐照钨作为核反应堆中使用的结构材料具有重要意义。使用耦合方法得出的结果与单轴拉伸试验的实验数据十分吻合。该模型能够捕捉温度和辐照剂量对材料硬化的影响。提出了两种估算硬度的方法--使用单轴屈服应力与硬度相关的泰伯定律以及平冲模拟。结果与辐照钨样品微压痕实验的硬度数据相当吻合。该模型还能揭示微观结构细节,如缺陷密度和局部应力的空间变化。
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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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