Dong Wang , Shihao Wu , Kai Lu , Yapei Zhang , G.H. Su , Xi Liu
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引用次数: 0
Abstract
In our previous studies of Cr-coated Zr alloy cladding, models for the oxidation and degradation of Cr coating and for the oxidation and phase transformation of Zr alloy have been established. On these foundations, oxygen flux models for Cr-Zr non-eutectic and eutectic conditions are developed in this paper, enabling a comprehensive simulation of the oxidation processes of Cr-coated Zr alloy. The models are validated through oxidation experiments under isothermal and temperature ramp conditions, showing good agreement with the experimental data. The models can effectively simulate the processes where, under non-eutectic conditions, oxygen atoms first dissolve into the prior β-Zr matrix after coating degradation, followed by the formation of α-Zr(O) and eventually ZrO2. For conditions with eutectic reaction, model assumption of immediate complete coating failure could lead to overestimation of substrate oxidation extent at low heating rates. This prediction deviation decreases as heating rate increases.
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.