Modeling and analysis for the anisotropic irradiation swelling of porous SiC/SiC composites

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Luning Chen, Jing Zhang, Shurong Ding
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引用次数: 0

Abstract

SiC/SiC composites are one of the promising engineering materials for nuclear applications. Anisotropic swelling deformations were observed in these materials during irradiation, and the underlying mechanisms should be deeply understood. In this study, a numerical simulation method is developed to predict the irradiation-induced deformations of the as-fabricated SiC/SiC composites. An emphasis is given to the generation of an RVE (Representative Volume Element) model with a pre-existing pore and the assumed residual stress field. Besides, the thermo-mechanical constitutive relations and stress update algorithms for the solid skeleton of porous SiC/SiC composites are developed with their irradiation effects considered comprehensively. Based on the homogenization theory, the calculation models to obtain the macroscopic swelling strains of porous SiC/SiC composites are developed. The good agreements between the predictions and the post-irradiation data of anisotropic swelling validate the effectiveness of the developed models and simulation methods. Research findings indicate that the irradiation creep deformations due to the existing residual stresses and high transient creep rate coefficients lead to the through-thickness size shrinkage of the pre-existing pores, which possibly becomes the dominant mechanism of the negative linear swelling of the SiC/SiC sample during the initial irradiation stage. The effects of the initial residual stress fields and the elastic constitutive relations on the anisotropic irradiation swelling behaviors are investigated. This study lays a foundation for the advanced manufacture of the SiC/SiC composites and the based multi-layer cladding tubes.
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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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