Shuai Wang , Ziyi Li , Baiming Yao , Hailin Zhai , Jishen Jiang , Xianfeng Ma , Wei-An Dang , Weizhong Fan , Zhen Wang
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引用次数: 0
Abstract
The mechanism for the enhancement of crack resistance and oxidation resistance in pre-annealed Cr-coated Zr-4 alloy with bars and plates was investigated. After annealing, the residual lattice strain and dislocation density of Cr coating were reduced due to recrystallization, which greatly prolonged the crack initiation strain in three-point bending experiments from 0.47 % to 5.21 %. Besides, Due to the reduction in grain boundary density, the inward diffusion paths of oxygen and ZrO2 precipitation were reduced in the coating, thereby delaying the oxidation process and enhancing the oxidation resistance upon annealing. However, the brittle ZrCr2 interlayer was formed after annealing at above 700 °C, which might weaken interfacial adhesion of Cr coating. The optimal annealing temperature was recommended as 650–700 °C.
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.