| 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 | 48 | 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 | 37 | 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 | 33 | 2017 |
| 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 | 16 | 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 |
| 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 |
| 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 | 12 | 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 | 9 | 2022 |
| 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, DS Sohn, Y Mok | 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 |
| 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, 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 |
| Effects of Preformed Oxide on Enhancing High-Temperature Oxidation Resistance of a Zirconium Alloy Cladding Tube CM Lee, TW Choa, GY Jeonga, MJ Kima, JH Kima, YK Mokb, DS Sohn | | 2018 |
| Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures CM Lee Graduate School of UNIST, 2018 | | 2018 |
| A new Method to Enhance the Oxidation Resistance of a Zirconium Alloy Cladding: High-Temperature Pre-Oxidation CM Lee, TW Cho, GY Jeong, M Kim, HJ Lee, JH Kim, DS Sohn 한국원자력학회, 2017 | | 2017 |
