Inversion of the fracture toughness of zirconium alloy cladding interface in nuclear fuel using splitting method via general regression neural network

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2024-12-17 DOI:10.1016/j.jnucmat.2024.155573
Yubo Zhou , Yingxuan Dong , Haojun Ma , Junnan Lv , Qun Li
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Abstract

For nuclear fuel elements, the interface mechanical properties of zirconium alloy cladding is critical to the safety and reliability of reactors. However, due to the small thickness of the fuel plates (<2 mm), accurately capturing the behavior of interface cracks is challenging, complicates the measurement of interface fracture toughness. This study developed a data-driven inversion method using the generalized regression neural network (GRNN) to rapidly and accurately determine the fracture toughness of zirconium alloy cladding interface. The database was established by combining splitting experiments with numerical simulations. The cohesive zone model was utilized to accurately simulate crack propagation paths and fracture modes in numerical simulations. The influences of key parameters such as cohesive strength, stiffness, and interface fracture energy were analyzed in detail. After extensive training, the prediction model accurately forecasted the interface fracture toughness. The results indicate that the proposed GRNN-based inversion approach is feasible and effective for predicting the fracture toughness of zirconium alloy cladding interface, and can be extended to determinations of other mechanical properties in the nuclear fuel element.
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基于广义回归神经网络的劈裂法反演核燃料锆合金包层界面断裂韧性
对于核燃料元件而言,锆合金包层的界面力学性能对反应堆的安全可靠性至关重要。然而,由于燃料板厚度较小(约2mm),准确捕捉界面裂纹行为具有挑战性,使界面断裂韧性的测量复杂化。本研究提出了一种基于广义回归神经网络(GRNN)的数据驱动反演方法,快速准确地确定锆合金熔覆界面断裂韧性。采用分裂实验和数值模拟相结合的方法建立了该数据库。在数值模拟中,采用内聚区模型准确地模拟了裂纹扩展路径和断裂模式。详细分析了黏结强度、刚度和界面断裂能等关键参数的影响。该预测模型经过大量训练,能够准确预测界面断裂韧性。结果表明,基于grnn的反演方法对锆合金包层界面断裂韧性的预测是可行和有效的,并可推广到核燃料元件其他力学性能的测定中。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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