氢致铀及铀合金机械降解研究进展

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Mengsheng Zhai, Sheng Zhang, Wenliang Xu, Hefei Ji, Lizhu Luo, Kunming Yang, Shushan Cui, Shilv Yu, Chuan Mo, Ruiwen Li, Dongli Zou, Dawu Xiao, Bin Su, Wenhua Luo
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引用次数: 0

摘要

在这篇综述中,我们研究了铀及其合金的氢腐蚀行为,重点研究了氢腐蚀对其力学性能的影响,包括氢脆和氢诱导应力腐蚀开裂(HISCC)。加入Nb和Mo等元素可以提高铀合金的抗氢腐蚀性能,从而降低氢脆和氢致应力腐蚀开裂的易感性。虽然关于高应变变形下铀氢脆的研究有限,但已有证据表明,提高应变速率可以缓解氢脆。氢脆和氢致应力腐蚀开裂的机制仍然存在争议,特别是关于铀氢化物的形成还是固溶体氢在脆化过程中起主导作用。未来的研究应将先进的表征技术与从原子尺度到连续尺度的多尺度建模相结合,以阐明这些机制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Review of hydrogen-induced mechanical degradation in uranium and uranium alloys
In this review, we examine the hydrogen corrosion behavior of uranium and its alloys, with a focus on its impact on their mechanical performance, including hydrogen embrittlement and hydrogen-induced stress corrosion cracking (HISCC). Alloying with elements such as Nb and Mo has been shown to improve hydrogen corrosion resistance of uranium alloys, thereby reducing susceptibility to hydrogen embrittlement and hydrogen-induced stress corrosion cracking. Although studies about uranium hydrogen embrittlement under high strain deformation remain limited, existing evidence suggests that increasing strain rate can alleviate hydrogen embrittlement. The mechanisms underlying hydrogen embrittlement and hydrogen-induced stress corrosion cracking in uranium are still under debate, particularly regarding whether uranium hydrides formation or solid-solution hydrogen plays the dominant role in the embrittlement process. Future research should integrate advanced characterization techniques with multiscale modelling, spanning from atomic scale to continuum scale, to elucidate these mechanisms.
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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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