| 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 | 330 | 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 | 309 | 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 | 265 | 2015 |
| Effect of β phase, precipitate and Nb-concentration in matrix on corrosion and oxide characteristics of Zr–xNb alloys YH Jeong, HG Kim, TH Kim Journal of Nuclear Materials 317 (1), 1-12, 2003 | 218 | 2003 |
| 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 | 179 | 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 | 160 | 2016 |
| Correlation between microstructure and corrosion behavior of Zr–Nb binary alloy YH Jeong, KO Lee, HG Kim Journal of Nuclear Materials 302 (1), 9-19, 2002 | 154 | 2002 |
| Influence of Nb concentration in the α-matrix on the corrosion behavior of Zr–xNb binary alloys YH Jeong, HG Kim, DJ Kim, BK Choi, JH Kim Journal of Nuclear Materials 323 (1), 72-80, 2003 | 128 | 2003 |
| 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 | 120 | 2014 |
| Corrosion and microstructural characteristics of Zr–Nb alloys with different Nb contents HG Kim, SY Park, MH Lee, YH Jeong, SD Kim Journal of Nuclear Materials 373 (1-3), 429-432, 2008 | 116 | 2008 |
| 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 | 115 | 2014 |
| Ex-reactor corrosion and oxide characteristics of Zr–Nb–Fe alloys with the Nb/Fe ratio HG Kim, JY Park, YH Jeong Journal of Nuclear Materials 345 (1), 1-10, 2005 | 109 | 2005 |
| Effect of isothermal annealing on the corrosion behavior of Zr–xNb alloys HG Kim, YH Jeong, TH Kim Journal of Nuclear Materials 326 (2-3), 125-131, 2004 | 109 | 2004 |
| Out-of-pile and in-pile perfomance of advanded zirconium alloys (HANA) for high burn-up fuel YH Jeong, SY Park, MH Lee, BK Choi, JH Baek, JY Park, JH Kim, HG Kim Journal of nuclear science and technology 43 (9), 977-983, 2006 | 102 | 2006 |
| Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs HG Kim, IH Kim, YI Jung, DJ Park, JH Park, BK Choi, YH Lee Journal of Nuclear Materials 510, 93-99, 2018 | 78 | 2018 |
| Oxidation characteristics of basal (0002) plane and prism (1120) plane in HCP Zr HG Kim, TH Kim, YH Jeong Journal of nuclear materials 306 (1), 44-53, 2002 | 77 | 2002 |
| Long-term corrosion behavior of CVD SiC in 360 C water and 400 C steam JY Park, IH Kim, YI Jung, HG Kim, DJ Park, WJ Kim Journal of nuclear materials 443 (1-3), 603-607, 2013 | 72 | 2013 |
| 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 | 71 | 2013 |
| A study of the breakaway oxidation behavior of zirconium cladding materials HG Kim, IH Kim, BK Choi, JY Park Journal of Nuclear Materials 418 (1-3), 186-197, 2011 | 68 | 2011 |
| Phase boundary of the Zr-rich region in commercial grade Zr–Nb alloys HG Kim, JY Park, YH Jeong Journal of nuclear materials 347 (1-2), 140-150, 2005 | 62 | 2005 |
Yang-Hyun KooExecutive editor of the journal of NET, KAERIkaeri.re.kr의 이메일 확인됨
