A finite element study on the irradiation-induced mechanical behaviors of aluminum-matrix radiation-shielding composites

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-02 DOI:10.1016/j.jnucmat.2024.155440

Jiaqing Shi , Zheng Lv , Jian Wang , Wentao Tang , Yufei Liu , Zenglin Yang , Jian Yang , Zhimin Yang , Shuwang Ma

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Abstract

Aluminum-matrix radiation-shielding composites play a crucial role in advanced nuclear energy systems and fuel containers owing to their shielding design flexibility and desired structural compatibility. After being irradiated by neutrons, the shielding composites undergo irradiation damage and exhibit irradiation-induced mechanical effects such as irradiation hardening and embrittlement, which directly threaten the industrial application of the material. In this study, a finite element method was used to investigate the irradiation-induced mechanical behavior of radiation-shielding B₄C_P-W_P/Al composites. Using published data on the post-irradiation mechanical property evolutions of the matrix and shielding particles, and incorporating mechanisms of irradiation hardening and embrittlement, a finite element model was developed to describe the deformation of pristine and post-irradiation composites. Simulations of the post-irradiation mechanical properties of the aluminum-matrix radiation-shielding composites were conducted. The simulation results successfully reproduced the experimental findings for both the Al matrix and composites after irradiation. Furthermore, the stress-strain responses and deformation behaviors of the composites at different stages of irradiation damage are discussed. Finally, based on the simulation results, an artificial neural network was trained to efficiently predict the irradiation-induced mechanical behavior of the composites.

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铝基辐射屏蔽复合材料辐照诱导力学行为的有限元研究

铝基辐射屏蔽复合材料因其屏蔽设计的灵活性和理想的结构兼容性，在先进核能系统和燃料容器中发挥着至关重要的作用。在受到中子辐照后，屏蔽复合材料会发生辐照损伤，表现出辐照诱导的力学效应，如辐照硬化和脆化，直接威胁到材料的工业应用。本研究采用有限元法研究了辐照诱导的辐照屏蔽 B4CP-WP/Al 复合材料的力学行为。利用已公布的基体和屏蔽粒子辐照后力学性能变化数据，并结合辐照硬化和脆化机理，建立了一个有限元模型来描述原始复合材料和辐照后复合材料的变形。对铝基辐照屏蔽复合材料辐照后的力学性能进行了模拟。模拟结果成功地再现了辐照后铝基体和复合材料的实验结果。此外，还讨论了复合材料在不同辐照损伤阶段的应力应变响应和变形行为。最后，根据模拟结果训练了一个人工神经网络，以有效预测复合材料在辐照诱导下的力学行为。

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来源期刊

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.