| Stacking Fault Energy Analyses of Additively Manufactured Stainless Steel 316L and CrCoNi Medium Entropy Alloy Using In Situ Neutron Diffraction W Woo, JS Jeong, DK Kim, CM Lee, SH Choi, JY Suh, SY Lee, S Harjo, ... Scientific reports 10 (1), 1350, 2020 | 89 | 2020 |
| Comparison of dislocation density, twin fault probability, and stacking fault energy between CrCoNi and CrCoNiFe medium entropy alloys deformed at 293 and 140K W Woo, M Naeem, JS Jeong, CM Lee, S Harjo, T Kawasaki, H He, ... Materials Science and Engineering: A 781, 139224, 2020 | 57 | 2020 |
| Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding CM Lee, DS Sohn Corrosion Science 131, 116-125, 2018 | 38 | 2018 |
| High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1 Fe fuel cladding CM Lee, YK Mok, DS Sohn Journal of Nuclear Materials 496, 343-352, 2017 | 35 | 2017 |
| Competitive strengthening between dislocation slip and twinning in cast-wrought and additively manufactured CrCoNi medium entropy alloys W Woo, YS Kim, HB Chae, SY Lee, JS Jeong, CM Lee, JW Won, YS Na, ... Acta Materialia 246, 118699, 2023 | 33 | 2023 |
| Synthesis of plasma-nitrided Cr coatings on HT9 steel for advanced chemical barrier property in a nuclear cladding application S Yeo, CM Lee, HS Yoon, JH Kim Applied Surface Science 579, 152133, 2022 | 22 | 2022 |
| Microstructural analysis of preformed oxides on a zirconium alloy before and after subsequent oxidation at 1000–1200° C CM Lee, HY Jeong, A Yoon, YK Mok, DS Sohn Corrosion Science 139, 410-420, 2018 | 13 | 2018 |
| Microstructural characteristics and different effects of 800–1200° C preformed oxides on high-temperature steam oxidation of a zirconium alloy cladding CM Lee, HY Jeong, A Yoon, YK Mok, DS Sohn Journal of Alloys and Compounds 753, 119-129, 2018 | 13 | 2018 |
| Effect of pre-strain on oxidation behaviour of nickel-based superalloys in air at 700 C CM Lee, YS Han, JS Jeong, WS Jung, SH Song, JS Kim Corrosion Science 200, 110229, 2022 | 12 | 2022 |
| Study of mechanism of oxidation resistance enhancement induced by preformed oxide on zirconium alloys CM Lee, YS Han, YK Mok, DS Sohn Corrosion Science 158, 108105, 2019 | 12 | 2019 |
| Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube” CM Lee, G Kim, DS Sohn, YS Han, YK Mok Journal of Nuclear Materials 526, 151749, 2019 | 7 | 2019 |
| Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditions CM Lee, HJ Lee, HG Kim, YK Mok, YS Han, DS Sohn Journal of Nuclear Materials 515, 80-90, 2019 | 7 | 2019 |
| Oxidation Resistance Enhancement of a Zirconium Alloy by High-Temperature Pre-Oxidation CM Lee, HJ Lee, TW Cho, GY Jeong, MJ Kim, JH Kim, Y Mok, DS Sohn Korea Nuclear Society Gyeongju, Korea, 2017 | 2 | 2017 |
| Oxidation Kinetics of the Zr-1Nb-1Sn-0.1 Fe at temperatures of 1000-1200ºC CM Lee, DS Sohn Korean Nuclear Society Autumn Meeting (KNS 2015), 2015 | 2 | 2015 |
| Ar-ion-and electron-irradiated ZrC layers in ZrC-SiC-coated surrogate TRISO fuel particles S Yeo, SJ Yoo, H Lee, JM Oh, CM Lee, JH Kim, E Kim, H Han, S Mhin Journal of the European Ceramic Society 44 (5), 2730-2743, 2024 | 1 | 2024 |
| Thermal creep analysis and correlation development for manufactured HT9 cladding DH Kim, CM Lee, JH Kim, SH Kim, S Yeo, YK Lee Journal of Nuclear Materials 593, 154999, 2024 | | 2024 |
| Preliminary Verification of Fuel Constituent Redistribution Model JH Kim, BO Lee, JS Kim, CM Lee, CB Lee, JS Cheon 한국방사성폐기물학회 학술논문요약집, 108-108, 2021 | | 2021 |
| Validity Analysis of a HT9 Creep Correlation CM Lee, D Kima, JH Kima, JH Kim, JS Cheon | | 2021 |
| Investigation of Fuel Pellet Interaction with Zirconium Dioxide and Fission Products in LWR CM Lee, S Yoon, J Park, H Ko, J Park, KH Park | | 2018 |
| Enhanced high-temperature performance of a zirconium alloy cladding by high-temperature preformed oxide CM Lee, YK Mok, DS Sohn American Nuclear Society, 2018 | | 2018 |
