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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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.
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.