Zr-Cr共晶反应对cr包覆ATF熔覆层结构完整性影响的评价

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Boyeon Kweon , Hyunwoo Yook , Dongju Kim , Youho Lee
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引用次数: 0

摘要

全面系统地评估了长时间高温蒸汽暴露下Zr-Cr共晶反应对cr包覆ATF包层结构完整性的潜在影响。不同涂层厚度(5、8、10、12、16、18µm)的cr包覆Zr-Nb合金在高于Zr-Cr共晶开始的温度下被蒸汽氧化长达2小时。即使在蒸汽氧化条件下长时间暴露,也没有观察到由共晶混合物(β-Zr+ZrCr2)引起的熔化流动或结构崩溃的证据。随着Zr基体中氧浓度的增加,共晶起始温度相应升高,导致共晶混合物凝固,在基体中以ZrCr2的形式存在。此外,即使在无氧惰性环境中,在测试涂层厚度范围内的cr量也不足以驱动共晶混合物穿过整个包层厚度(570µm)。为了评估与潜在结构失效相关的安全裕度,开发了一个简单而准确的模型来预测cr限制共晶厚度作为初始涂层厚度的函数,并进行了实验验证。根据该模型,要在整个包层壁上形成共晶混合物,Cr涂层厚度需要达到~ 72µm。即使考虑到部分增厚的共晶反应区(“厚区”),涂层也需要超过~ 49µm才能达到全厚度。这些发现表明,在目前考虑用于商业应用的涂层厚度(~ 15-20µm)下,共晶起始温度下的安全问题应该集中在氧化引起的脆化上,而不是共晶熔化引起的坍塌。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Assessment of the impact of Zr-Cr eutectic reaction on the structural integrity of Cr-coated ATF cladding
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.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
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.
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