| Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating HG Kim, IH Kim, YI Jung, DJ Park, JY Park, YH Koo Journal of Nuclear Materials 465, 531-539, 2015 | 380 | 2015 |
| Development status of accident-tolerant fuel for light water reactors in Korea HG Kim, JH Yang, WJ Kim, YH Koo Nuclear Engineering and Technology 48 (1), 1-15, 2016 | 326 | 2016 |
| High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings JH Park, HG Kim, J Park, YI Jung, DJ Park, YH Koo Surface and Coatings Technology 280, 256-259, 2015 | 295 | 2015 |
| Radioactivity release from the Fukushima accident and its consequences: A review YH Koo, YS Yang, KW Song Progress in Nuclear Energy 74, 61-70, 2014 | 197 | 2014 |
| A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment DJ Park, HG Kim, JY Park, YI Jung, JH Park, YH Koo Corrosion Science 94, 459-465, 2015 | 195 | 2015 |
| Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions DJ Park, HG Kim, YI Jung, JH Park, JH Yang, YH Koo Journal of nuclear materials 482, 75-82, 2016 | 177 | 2016 |
| Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel development HS Kim, CY Joung, BH Lee, JY Oh, YH Koo, P Heimgartner Journal of Nuclear Materials 378 (1), 98-104, 2008 | 154 | 2008 |
| KAERI’s development of LWR accident-tolerant fuel YH Koo, JH Yang, JY Park, KS Kim, HG Kim, DJ Kim, YI Jung, KW Song Nuclear technology 186 (2), 295-304, 2014 | 131 | 2014 |
| Oxidation behavior of silicon carbide at 1200 C in both air and water–vapor-rich environments DJ Park, YI Jung, HG Kim, JY Park, YH Koo Corrosion science 88, 416-422, 2014 | 128 | 2014 |
| Fabrication of micro-cell UO2–Mo pellet with enhanced thermal conductivity DJ Kim, YW Rhee, JH Kim, KS Kim, JS Oh, JH Yang, YH Koo, KW Song Journal of Nuclear Materials 462, 289-295, 2015 | 112 | 2015 |
| Application of coating technology on zirconium-based alloy to decrease high-temperature oxidation HG Kim, IH Kim, JY Park, YH Koo 17th International Symposium on Zirconium in the Nuclear Industry, Andhra …, 2013 | 75 | 2013 |
| Pore pressure and swelling in the rim region of LWR high burnup UO2 fuel YH Koo, BH Lee, JS Cheon, DS Sohn Journal of Nuclear Materials 295 (2-3), 213-220, 2001 | 75 | 2001 |
| UO2–UN composites with enhanced uranium density and thermal conductivity JH Yang, DJ Kim, KS Kim, YH Koo Journal of Nuclear Materials 465, 509-515, 2015 | 56 | 2015 |
| COSMOS: a computer code to analyze LWR UO2 and MOX fuel up to high burnup YH Koo, BH Lee, DS Sohn Annals of Nuclear Energy 26 (1), 47-67, 1999 | 55 | 1999 |
| High-temperature oxidation behavior of Cr-coated zirconium alloy HG Kim, IH Kim, YI Jung, DJ Park, JY Park, YH Koo Proceeding of LWR Fuel Performance Meeting/TopFuel, Charlotte, USA 842, 846, 2013 | 53 | 2013 |
| State-of-the-art report on light water reactor accident-tolerant fuels K Pasamehmetoglu, S Massara, D Costa, S Bragg-Sitton, M Moatti, ... Organisation for Economic Co-Operation and Development, 2018 | 48 | 2018 |
| Development status of microcell UO2 pellet for accident-tolerant fuel DJ Kim, KS Kim, DS Kim, JS Oh, JH Kim, JH Yang, YH Koo Nuclear Engineering and Technology 50 (2), 253-258, 2018 | 46 | 2018 |
| Analysis of fission gas release and gaseous swelling in UO2 fuel under the effect of external restraint YH Koo, BH Lee, DS Sohn Journal of nuclear materials 280 (1), 86-98, 2000 | 44 | 2000 |
| Microstructure and mechanical behavior of Zr substrates coated with FeCrAl and Mo by cold-spraying DJ Park, HG Kim, YI Jung, JH Park, JH Yang, YH Koo Journal of Nuclear Materials 504, 261-266, 2018 | 42 | 2018 |
| Microstructure and mechanical strength of surface ODS treated Zircaloy-4 sheet using laser beam scanning HG Kim, IH Kim, YI Jung, DJ Park, JY Park, YH Koo Nuclear engineering and Technology 46 (4), 521-528, 2014 | 42 | 2014 |