多场耦合下表面涂层 Zircaloy-4 包层的弹塑性力学行为分析

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Xin Wang, Ze Xu, Yulan Liu, Biao Wang
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引用次数: 0

摘要

在多场耦合效应下,探讨了表面镀铬(Cr)或铁铬铝(FeCrAl)的锆合金-4(Zr-4)包层的弹塑性机械行为。利用有限元软件 ABAQUS,模拟计算了两个完整燃料循环过程中应力和应变的演变。对有涂层和无涂层的 Zircaloy-4 包层材料进行了比较。结果表明,在第一个燃料循环期间,表面涂层的应用大大减轻了包层的应力水平。在第二个燃料循环期间,所有三种类型的包层都表现出相对较小的塑性应变,这归因于循环之间的卸载和再装载过程。值得注意的是,塑性区从包层内部向外部扩展。与传统的 Zircaloy-4 包层相比,涂层包层的弹塑性机械性能得到了改善。此外,还研究了涂层在圆柱坐标不同应力下的运行机制及其对卸载和再装载循环的响应。具体而言,与未涂覆覆层相比,涂覆覆层在达到完全塑性方面表现出明显的延迟。此外,FeCrAl 涂层材料初步显示出良好的性能,今后还需要在更多方面进行验证。本文的结果和结论可为今后的实验提供参考和指导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Elastoplastic mechanical behavior analysis of surface-coated Zircaloy-4 cladding under multi-field coupling
The elastoplastic mechanical behavior of Zircaloy-4 (Zr-4) cladding, coated with chromium (Cr) or FeCrAl on its surface, is explored under the coupled effects of multi-field coupling. Utilizing the Finite Element Software ABAQUS, simulations are conducted to calculate the evolution of stress and strain over two complete fuel cycles. Comparisons are drawn between the coated and uncoated Zircaloy-4 cladding materials. The results indicate that the application of surface coatings significantly mitigates stress levels in the cladding during the first fuel cycle. During the second fuel cycle, all three types of cladding exhibit relatively minor plastic strain, which is attributed to the unloading and reloading process between cycles. Notably, the plastic zone propagates from the interior to the exterior of the cladding. When compared to traditional Zircaloy-4 cladding, the coated cladding exhibits improved elastoplastic mechanical behavior. The operational mechanism of the coating for different stresses in cylindrical coordinates and its response to unloading and reloading cycles are also investigated. Specifically, the coated claddings exhibit an evident delay in reaching full plasticity compared to uncoated claddings. Furthermore, FeCrAl coating material initially shows good performance, and it needs to be verified in more aspects in the future. Results and Conclusions in this paper can provide reference and guidance for future experiments.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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