Boyeon Kweon , Hyunwoo Yook , Dongju Kim , Youho Lee
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引用次数: 0
Abstract
The potential impact of the Zr-Cr eutectic reaction on the structural integrity of Cr-coated ATF cladding under prolonged high-temperature steam exposure was comprehensively and systematically assessed. Cr-coated Zr-Nb alloys with various coating thicknesses (5, 8, 10, 12, 16, 18 µm) were subjected to steam oxidation at temperatures above the Zr-Cr eutectic onset for up to 2 h. No evidence of melting flow or structural collapse attributable to the eutectic mixture (β-Zr+ZrCr2) was observed, even after extended exposure under steam-oxidizing conditions. As the oxygen concentration in the Zr matrix increased, the corresponding rise in eutectic onset temperature led to solidification of the eutectic mixture, which remained as ZrCr2 within the matrix. Furthermore, even in an oxygen-free inert environment, the amount of Cr—within the tested coating thickness range—was insufficient to drive eutectic mixture through the entire cladding thickness (570 µm). To assess safety margins related to potential structural failure, a straightforward yet accurate model was developed to predict the Cr-limited eutectic thickness as a function of initial coating thickness, and was experimentally validated. According to the model, a Cr coating thickness of ∼72 µm would be required to form the eutectic mixture across the entire cladding wall. Even when accounting for the partially thickened eutectic reaction region (‘Thick zone’), the coating would need to exceed ∼49 µm reach full thickness. These findings suggest that, at coating thicknesses currently considered for commercial application (∼15–20 µm), safety concerns at the eutectic onset temperature should focus on oxidation-induced embrittlement rather than eutectic melting-induced collapse.
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.