| Temperature effect on the creep behavior of alloy 617 in air and helium environments WG Kim, JY Park, GG Lee, SD Hong, YW Kim Nuclear Engineering and Design 271, 291-300, 2014 | 27 | 2014 |
| Microstructural investigation of Alloy 617 creep-ruptured at high temperature in a helium environment GG Lee, S Jung, JY Park, WG Kim, SD Hong, YW Kim Journal of Materials Science & Technology 29 (12), 1177-1183, 2013 | 24 | 2013 |
| A novel process for fabrication of SnO2-based thick film gas sensors S Lee, GG Lee, J Kim, SJL Kang Sensors and Actuators B: Chemical 123 (1), 331-335, 2007 | 24 | 2007 |
| Modeling of sink-induced irradiation growth of single-crystal and polycrystal zirconiums in nuclear reactors SI Choi, GG Lee, J Kwon, JH Kim Journal of Nuclear Materials 468, 56-70, 2016 | 22 | 2016 |
| Material characterization of Ni base alloy for very high temperature reactor DJ Kim, GG Lee, DJ Kim, SJ Jeong Journal of Materials Science & Technology 29 (12), 1184-1190, 2013 | 22 | 2013 |
| Formation of large pores and their effect on electrical properties of SnO2 gas sensors GG Lee, SJL Kang Sensors and Actuators B: Chemical 107 (1), 392-396, 2005 | 20 | 2005 |
| Proton irradiation for radiation-induced changes in microstructures and mechanical properties of austenitic stainless steel HH Jin, SS Hwang, MJ Choi, GG Lee, J Kwon Journal of Nuclear Materials 513, 271-281, 2019 | 17 | 2019 |
| The use of Thermodynamics and Phase Equilibria for Prediction of the Behavior of High Temperature Corrosion of Alloy 617 in Impure Helium Environment DJ Kim, GG Lee, SW Kim, HP Kim Corrosion Science and Technology 9 (4), 164-170, 2010 | 16 | 2010 |
| Investigation on material degradation of alloy 617 in high temperature impure helium coolant DJ Kim, GG Lee, SJ Jeong, WG Kim, JY Park Nuclear Engineering and Technology 43 (5), 429-436, 2011 | 15 | 2011 |
| Microstructural investigation of Alloy 617 corroded in high-temperature helium environment GG Lee, S Jung, D Kim, YW Jeong, DJ Kim Nuclear Engineering and Design 271, 301-308, 2014 | 14 | 2014 |
| Multiscale modeling of radiation effects on materials: pressure vessel embrittlement JH Kwon, GG Lee, CS Shin Nuclear Engineering and Technology 41 (1), 11-20, 2009 | 14 | 2009 |
| Machine learning modeling of irradiation embrittlement in low alloy steel of nuclear power plants GG Lee, MC Kim, BS Lee Nuclear Engineering and Technology 53 (12), 4022-4032, 2021 | 12 | 2021 |
| Observation and rate theory modeling of grain boundary segregation in Σ3 twin boundaries in ion-irradiated stainless steel 316 GG Lee, HH Jin, YB Lee, J Kwon Journal of Nuclear Materials 449 (1-3), 234-241, 2014 | 12 | 2014 |
| Analysis of texture and grain shape effects on the yield anisotropy of Zr-2.5 wt% Nb pressure tube alloy using crystal plasticity finite element method DH Ahn, GG Lee, J Moon, HS Kim, YB Chun Journal of Nuclear Materials 555, 153112, 2021 | 11 | 2021 |
| Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in … WC Cheng, T Sakurahara, S Zhang, P Farshadmanesh, S Reihani, E Kee, ... Progress in Nuclear Energy 118, 103105, 2020 | 10 | 2020 |
| Flow-accelerated corrosion assessment for SA106 and SA335 pipes with elbows and welds DJ Kim, SW Kim, JY Lee, KM Kim, SB Oh, GG Lee, J Kim, SS Hwang, ... Nuclear Engineering and Technology 53 (9), 3003-3011, 2021 | 9 | 2021 |
| Study on the mechanical properties and microstructure of Zr-2.5 wt% Nb pressure tube material DH Ahn, S Lim, GG Lee, YB Chun Journal of Nuclear Materials 523, 458-471, 2019 | 9 | 2019 |
| Effect of Inhomogeneous Nucleation of Hydride at α/β Phase Boundary on Microstructure Evolution of Zr–2.5 wt% Nb Pressure Tube SS Kim, S Lim, DH Ahn, GG Lee, K Chang Metals and Materials International 25, 838-845, 2019 | 8 | 2019 |
| Radiation damage to Ni-based alloys in Wolsong CANDU reactor environments J Kwon, HH Jin, GG Lee, DH Park Nuclear Engineering and Technology 51 (3), 915-921, 2019 | 8 | 2019 |
| A phase-field modeling of void swelling in the Austenitic stainless steel K Chang, GG Lee, J Kwon Radiation Effects and Defects in Solids 171 (3-4), 242-251, 2016 | 8 | 2016 |
