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Hyeong-Yeon Lee

Observed names: Hyeong‐Yeon Lee, 이형언, 이형연
ORCID: 0000-0002-1932-3163
Observed ORCID: 0000-0002-1932-3163
OpenAlex ID: A5033713505
Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
2016 · Seok-Kyu Chang, Dong-Jin Euh, et al. · Nuclear Engineering and Technology · 45
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Treatment of residual stress in failure assessment procedure
2006 · Hyeong-Yeon Lee, Farid R. Biglari, et al. · Engineering Fracture Mechanics · 36
Thermal ratchetting deformation of a 316L stainless steel cylindrical structure under an axial moving temperature distribution
2003 · Hyeong-Yeon Lee, Jong-Bum Kim, et al. · International Journal of Pressure Vessels and Piping · 35
Evaluation of tension and creep rupture behaviors of long-term exposed P91 steel in a supercritical plant
2020 · Woo-Gon Kim, Hyeong-Yeon Lee, et al. · Engineering Failure Analysis · 30
Comparison of elevated temperature design codes of ASME Subsection NH and RCC-MRx
2016 · Hyeong-Yeon Lee · Nuclear Engineering and Design · 29
Preliminary application of the draft code case for alloy 617 for a high temperature component
2008 · Hyeong-Yeon Lee, Yong-Wan Kim, et al. · Journal of Mechanical Science and Technology · 25
Investigations of single-phase flow mixing characteristics in a wire-wrapped 37-pin bundle for a sodium-cooled fast reactor
2015 · Hyungmo Kim, Hwang Bae, et al. · Annals of Nuclear Energy · 23
Creep-fatigue damage evaluation of sodium to air heat exchanger in sodium test loop facility
2012 · Hyeong-Yeon Lee, Jong-Bum Kim, et al. · Nuclear Engineering and Design · 23
Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method
2017 · Seok-Kyu Chang, Dong-Jin Euh, et al. · Annals of Nuclear Energy · 22
Time-dependent crack growth behavior for a SMAW weldment of Gr. 91 steel
2013 · Woo-Gon Kim, Jae-Young Park, et al. · International Journal of Pressure Vessels and Piping · 20
High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger
2012 · Hyeong-Yeon Lee, Jong-Bum Kim, et al. · Journal of Pressure Vessel Technology · 19
Status of HCCR TBM program for DEMO blanket
2021 · Seungyon Cho, Mu-Young Ahn, et al. · Fusion Engineering and Design · 18
Seismic base isolation technologies for Korea advanced liquid metal reactor
2000 · Bong Yoo, Jae-Han Lee, et al. · Nuclear Engineering and Design · 18
Elevated temperature design and integrity evaluation of a large-scale sodium test facility, STELLA-2
2019 · Hyeong-Yeon Lee, Jaehyuk Eoh, et al. · Nuclear Engineering and Design · 17
High-temperature material properties of type 316L stainless steel for the design of pressure boundary components subjected to 700°C coolant
2024 · Hyeong-Yeon Lee, Ki-Ean Nam, et al. · Nuclear Engineering and Technology · 15
Design of type 316L stainless steel 700 °C high-temperature piping
2023 · Hyeong-Yeon Lee, Hyeonil Kim, et al. · Nuclear Engineering and Technology · 13
Assessment of a creep-fatigue crack initiation and crack propagation for a welded cylindrical shell
2006 · Hyeong-Yeon Lee, Jong-Bum Kim, et al. · International Journal of Pressure Vessels and Piping · 13
Evaluation of progressive inelastic deformation induced by a moving axial temperature front for a welded structure
2004 · Hyeong-Yeon Lee, Jong-Bum Kim, et al. · International Journal of Pressure Vessels and Piping · 13
Assessment of subchannel flow mixing coefficients for wire-wrapped hexagonal fuel rod bundles
2021 · Sun Rock Choi, Hyungmo Kim, et al. · Annals of Nuclear Energy · 12
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High temperature design of finned-tube sodium-to-air heat exchanger in a sodium test loop
2013 · Hyeong-Yeon Lee, Jae-Hyuk Eoh, et al. · Nuclear Engineering and Design · 12
Creep-fatigue crack behaviour of a mod. 9Cr-1Mo steel structure with weldments
2010 · Hyeong-Yeon Lee, Jong-Bum Kim, et al. · Transactions of the Indian Institute of Metals · 12
Development of a program for high-temperature design evaluation according to RCC-MRx
2017 · Hyeong-Yeon Lee, Min-Gu Won, et al. · Nuclear Engineering and Design · 11
Design and thermal-hydraulic evaluation of the finned-tube type sodium-to-air heat exchanger in sodium test facility
2020 · Hyungmo Kim, Jung Yoon, et al. · Nuclear Engineering and Design · 10
Risks of non-conservative design according to ASME B31.1 for high-temperature piping subjected to long-term operation in the creep range
2019 · Hyeong-Yeon Lee, Seok-Kwon Son, et al. · Nuclear Science and Techniques · 10
Effects of long-time service at high temperature on the material strength and J-R curve of Grade 91 steel
2017 · Hyeong-Yeon Lee, Dong-Won Lim, et al. · Engineering Fracture Mechanics · 10
Works count: 118
Citation count: 680
H-index: 15
I10-index: 26
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