| Corrosion and corrosion fatigue behaviors of 9Cr steel in a supercritical water condition Y Yi, B Lee, S Kim, J Jang Materials Science and Engineering: A 429 (1-2), 161-168, 2006 | 119 | 2006 |
| Potentiodynamic polarization behaviour of AISI type 316 stainless steel in NaCl solution Y Yi, P Cho, A Al Zaabi, Y Addad, C Jang Corrosion Science 74, 92-97, 2013 | 115 | 2013 |
| Passivity breakdown of 316L stainless steel during potentiodynamic polarization in NaCl solution S Al Saadi, Y Yi, P Cho, C Jang, P Beeley Corrosion Science 111, 720-727, 2016 | 109 | 2016 |
| Detection and evaluation of material degradation of thermally aged duplex stainless steels: electrochemical polarization test and AFM surface analysis YS Yi, T Shoji Journal of Nuclear Materials 231 (1-2), 20-28, 1996 | 49 | 1996 |
| Ultimate pressure capacity of nuclear reactor containment buildings under unaged and aged conditions S Alhanaee, Y Yi, A Schiffer Nuclear engineering and design 335, 128-139, 2018 | 33 | 2018 |
| Critical conditions for pit initiation and growth of austenitic stainless steels M Al Ameri, Y Yi, P Cho, S Al Saadi, C Jang, P Beeley Corrosion Science 92, 209-216, 2015 | 33 | 2015 |
| Oxidation rate of advanced heat-resistant steels for ultra-supercritical boilers in pressurized superheated steam YS Yi, Y Watanabe, T Kondo, H Kimura, M Sato J. Pressure Vessel Technol. 123 (3), 391-397, 2001 | 28 | 2001 |
| Measurement of the fundamental parameters for the film-rupture/oxidation mechanism SA Attanasio, JS Fish, DS Morton, PM Rosecrans, GS Was, ... Knolls Atomic Power Lab., Niskayuna, NY (US), 1999 | 24 | 1999 |
| Quantitative evaluation of material degradation of thermally aged duplex stainless steels using chemical immersion test YS Yi, T Shoji Journal of Nuclear Materials 240 (1), 62-69, 1996 | 23 | 1996 |
| Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment J Chen, A Nurrochman, JD Hong, TS Kim, C Jang, Y Yi Nuclear Engineering and Technology 51 (2), 479-489, 2019 | 20 | 2019 |
| Dry storage of spent nuclear fuel in UAE–Economic aspect S Al Saadi, Y Yi Annals of Nuclear Energy 75, 527-535, 2015 | 18 | 2015 |
| Theoretical SCC crack growth prediction under various loading modes in high temperature water S Suzuki, T Shoji, YS Yi, JK Kim Proc. 8th Int. Symp. Environmental Degradation of Materials in Nuclear Power …, 1997 | 17 | 1997 |
| Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis A Alraisi, Y Yi, S Lee, SA Alameri, M Qasem, CY Paik, C Jang Annals of Nuclear Energy 165, 108784, 2022 | 14 | 2022 |
| Stress and temperature dependence of creep in Alloy 600 in primary water Y Yi, GS Was Metallurgical and Materials Transactions A 32, 2553-2560, 2001 | 13 | 2001 |
| Steam oxidation of ferritic heat-resistant steels for ultra supercritical boilers Y Watanabe, Y Yi, T Kondo, K Suzuki, K Kano Zairyo-to-Kankyo 50 (2), 50-56, 2001 | 13 | 2001 |
| Nickel boride (NiB) as an inhibitor for an IGSCC of Alloy 600 and its applicability Y Yi, S Eom, H Kim, J Kim Journal of nuclear materials 347 (1-2), 151-160, 2005 | 12 | 2005 |
| Characterization methods of grain boundary and triple junction distributions YS Yi, JS Kim Scripta materialia 50 (6), 855-859, 2004 | 12 | 2004 |
| Effect of Cr content on supercritical water corrosion of high Cr alloys JS Jang, YB Lee, CH Han, YS Yi, SS Hwang Materials Science Forum 475, 1483-1486, 2005 | 11 | 2005 |
| Creep of nickel base alloys in high temperature water Y Yi, GS Was, J Cookson, JS Fish, SA Attanasio, HT Krasodomski, ... Proceedings of the Ninth International Symposium on Environmental …, 1999 | 10 | 1999 |
| An evaluation of potential material–coolant compatibility for applications in advanced fusion reactors T Kondo, Y Watanabe, YS Yi, A Hishinuma Journal of nuclear materials 258, 2083-2087, 1998 | 8 | 1998 |
