FeCrAlMo-xZr燃料包层合金热腐蚀过程的显微组织与力学演化

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chundong Wang , Xijie Wu , Jie Pan , Huawei Zhang , Jun Li , Jiwei Lin , Ping Cao , Cheng Su , Cong Li , Meiyi Yao , Xueshan Xiao
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引用次数: 0

摘要

研究了Fe-13Cr-6Al-2Mo-xZr (x = 0.15, 0.5, 1.0 wt%)燃料包壳合金在475℃空气热时效和1200℃Ar +水蒸气气氛下的高温氧化等不同热腐蚀过程中的组织和力学演变。结果表明,随着Zr含量的增加,合金的晶粒尺寸逐渐变小。热时效过程中,晶粒内析出二次Laves相,晶界上Mo发生偏析,最终形成μ相。随着时效时间的延长,由于析出相的形成和生长,塑性逐渐降低,而拉伸强度仅在时效初期有所增加,之后基本保持不变。随着Zr含量的增加,ZrO2晶粒尺寸变小,ZrO2中氧的扩散速度比Al2O3中快,内部氧化程度加深,水蒸气氧化速率加快。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion

Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion
The microstructural and mechanical evolution of the Fe-13Cr-6Al-2Mo-xZr (x = 0.15, 0.5, 1.0 wt%) alloys for fuel cladding throughout various hot corrosion processes, such as thermal aging at 475 °C in air and high temperature oxidation at 1200 °C under an atmosphere of Ar + water vapour, were investigated. The findings indicate that as the Zr content increases, the grain size of the alloys becomes progressively smaller. During thermal aging, the secondary Laves phase precipitated within the grains and Mo segregation occurred on the grain boundaries, ultimately forming the μ phase. The plasticity decreased by degrees with aging time due to the formation and growth of precipitates, while the tensile strength increased only during the early aging period and then remained almost unchanged. The steam oxidation rate was promoted with the Zr content because of the smaller grain size and the deeper internal oxidation resulting from the faster diffusion of oxygen in ZrO2 than that in Al2O3.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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