Development and application of an efficient method for performing modal analysis of steam generator tubes in nuclear power plants

Rhee, Hyug-Gyo; Boo, Myung-Hwan; Park, Chi-Yong; Ryu, Kyeong Seon

doi:10.1016/j.nucengdes.2010.07.022

Nuclear Engineering and Design

2010

DOI: 10.1016/j.nucengdes.2010.07.022

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Development and application of an efficient method for performing modal analysis of steam generator tubes in nuclear power plants

Hyug-Gyo Rhee

Myung-Hwan Boo

Chi-Yong Park

et al.

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Cited by 9 publications

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Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water

Zhuang,

Han,

Huang

et al. 2024

Journal of Nuclear Materials

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Development and application of an efficient method for performing modal analysis of steam generator tubes in nuclear power plants

Cited by 9 publications

References 2 publications

Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water

Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water

The role of frequency on fretting corrosion of Alloy 690TT against 304 stainless steel in high temperature high pressure water

Seismic analysis based structure integrity assessment of steam generator in fast breeder reactor

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