研究论文
Correlation between impact angle and corrosion-erosion damage behavior of ferritic/martensitic steel exposed to flowing oxygen-saturated lead-bismuth eutectic
Qi Sun, Xuechao Zheng, Qin Yu, Jifan He, Yanxiang Liang, Minhao Zhu
Southwest Jiaotong University China Academy of Engineering Physics
来源Journal of Nuclear Materials
年份2023
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材料 / 化学Nuclear Materials and Properties
Fusion materials and technologies · Nuclear reactor physics and engineering
参考文献 33
Multiscale investigation of quasi-brittle fracture characteristics in a 9Cr–1Mo ferritic–martensitic steel embrittled by liquid lead–bismuth under low cycle fatigue
被引 74Xing Gong, P. Marmy, Alexander Volodin · Corrosion Science · 2015
T91 cladding tubes with and without modified FeCrAlY coatings exposed in LBE at different flow, stress and temperature conditions
被引 234A. Weisenburger, A. Heinzel, Georg Müller · Journal of Nuclear Materials · 2008
Corrosion behavior of Si-enriched steels for nuclear applications in liquid lead–bismuth
被引 74Yuji Kurata · Journal of Nuclear Materials · 2013
此处列出前 3 条
引用本文 10
Insights into corrosion mechanism of FeCrAlY coating in oxygen-poor static and flowing LBE
被引 15Mingyang Zhou, Wei Zhang, Jiuguo Deng · Corrosion Science · 2024
Failure analysis of erosion wear of the pipeline after 30° elbow by adsorbent particles
被引 12Guoqing Su, Jianwen Zhang · Engineering Failure Analysis · 2024
Insight into the fretting corrosion behavior of 316L steel in liquid lead-bismuth eutectic at 500°C
被引 10Qi Sun, Qin Yu, Xiaoqiang Fan · Journal of Nuclear Materials · 2024
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