Bo Li , Jingjie Shen , Zongda Yang , Huilong Yang , Sho Kano , Hiroaki Abe
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引用次数: 0
Abstract
This study investigates the interfacial evolution of Cr/Mo-coated Zr alloys near the Mo-Zr eutectoid temperature, from the viewpoints of microstructure and chemical composition and with the joint application of XRD, TEM and EDS analyses. The experimental findings highlight significant changes in microstructure and diffusion behavior associated with the Mo-Zr eutectoid reaction. In the as-fabricated specimen, it is noted that introducing a Mo-intermediate layer results in the formation of an amorphous Cr layer at the Cr/Mo interface. In the case of the annealing temperature below the Mo-Zr eutectoid reaction, Mo interlayer effectively impedes the diffusion between Cr and Zr, thereby suppressing the formation of intermetallic compounds. However, the diffusion barrier function of Mo interlayer deteriorates when the temperature exceeds the eutectoid point, with the presence of four distinct diffusion zones, including α-Zr, β-Zr, the intermetallic compound Zr(Mo,Cr,Fe)₂, and the Mo layer containing fine Zr(Mo,Cr,Fe)2 particles. These findings underscore the critical role of Mo-interlayer in influencing the structural stability and intermetallic compound formation in Cr/Mo-coated Zr alloys, not only at the temperature regime around the eutectic reaction, but also at the temperature regime around the eutectoid reaction, which is of great necessity for the practical applications of accident tolerant fuel cladding under high temperature environment.
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.