| Corrosion behaviors of four stainless steels with similar chromium content in supercritical carbon dioxide environment at 650 C H Chen, SH Kim, C Kim, J Chen, C Jang Corrosion Science 156, 16-31, 2019 | 79 | 2019 |
| Characterization of interfacial reactions and oxide films on 316L stainless steel in various simulated PWR primary water environments J Chen, Q Xiao, Z Lu, X Ru, H Peng, Q Xiong, H Li Journal of Nuclear Materials 489, 137-149, 2017 | 68 | 2017 |
| Improving the oxidation resistance of 316L stainless steel in simulated pressurized water reactor primary water by electropolishing treatment G Han, Z Lu, X Ru, J Chen, Q Xiao, Y Tian Journal of Nuclear Materials 467, 194-204, 2015 | 57 | 2015 |
| Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor H Chen, H Wang, Q Sun, C Long, T Wei, SH Kim, J Chen, C Kim, C Jang Corrosion Science 145, 90-99, 2018 | 55 | 2018 |
| The effects of hydrogen on anodic dissolution and passivation of iron in alkaline solutions A Ejaz, Z Lu, J Chen, Q Xiao, X Ru, G Han, T Shoji Corrosion Science 101, 165-181, 2015 | 54 | 2015 |
| The effects of cold rolling orientation and water chemistry on stress corrosion cracking behavior of 316L stainless steel in simulated PWR water environments J Chen, Z Lu, Q Xiao, X Ru, G Han, Z Chen, B Zhou, T Shoji Journal of Nuclear Materials 472, 1-12, 2016 | 53 | 2016 |
| Characterization of microstructure of A508III/309L/308L weld and oxide films formed in deaerated high-temperature water Q Xiong, H Li, Z Lu, J Chen, Q Xiao, J Ma, X Ru Journal of Nuclear Materials 498, 227-240, 2018 | 47 | 2018 |
| Corrosion behavior of stainless steels in simulated PWR primary water: The effect of composition and matrix phases Q Xiao, C Jang, C Kim, H Kim, J Chen, HB Lee Corrosion Science 177, 108991, 2020 | 41 | 2020 |
| The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen J Chen, Z Lu, F Meng, X Xu, Q Xiao, HS Kim, C Jang Journal of Nuclear Materials 517, 179-191, 2019 | 40 | 2019 |
| Characterization of microstructure, local deformation and microchemistry in Alloy 690 heat-affected zone and stress corrosion cracking in high temperature water Z Lu, J Chen, T Shoji, Y Takeda, S Yamazaki Journal of Nuclear Materials 465, 471-481, 2015 | 36 | 2015 |
| Properties of oxide films formed on 316L SS and model alloys with modified Ni, Cr and Si contents in high temperature water G Han, Z Lu, X Ru, J Chen, J Zhang, T Shoji Corrosion Science 106, 157-171, 2016 | 34 | 2016 |
| Effect of heat treatment on corrosion behaviour of additively manufactured 316L stainless steel in high-temperature water Q Xiao, J Chen, HB Lee, C Jang, K Jang Corrosion Science 210, 110830, 2023 | 23 | 2023 |
| Supercritical-CO2 corrosion behavior of alumina-and chromia-forming heat resistant alloys with Ti GO Subramanian, SH Kim, J Chen, C Jang Corrosion Science 188, 109531, 2021 | 23 | 2021 |
| Magnetoelectropolishing treatment for improving the oxidation resistance of 316L stainless steel in pressurized water reactor primary water Q Xiao, Z Lu, J Chen, J Ma, Q Xiong, H Li, J Xu, T Shoji Journal of Nuclear Materials 518, 357-369, 2019 | 22 | 2019 |
| The effects of temperature and aeration on the corrosion of A508III low alloy steel in boric acid solutions at 25–95° C Q Xiao, Z Lu, J Chen, M Yao, Z Chen, A Ejaz Journal of Nuclear Materials 480, 88-99, 2016 | 21 | 2016 |
| 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 |
| Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water J Chen, C Jang, BS Kong, Q Xiao, GO Subramanian, HS Kim, JH Shin Corrosion Science 172, 108730, 2020 | 19 | 2020 |
| Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment HS Kim, HB Lee, J Chen, C Jang, TS Kim, GL Stevens, K Ahluwalia Corrosion Science 151, 97-107, 2019 | 19 | 2019 |
| Characterization of oxide layers formed on type 316 stainless steel exposed to the simulated PWR primary water environment with varying dissolved hydrogen and zinc concentrations HB Lee, J Chen, S Meng, C Jang, SH Park, Q Xiao, HJ Lee, KH Na Journal of Nuclear Materials 556, 153193, 2021 | 17 | 2021 |
| Evaluation of thermal ageing activation energy of δ-ferrite in an austenitic stainless steel weld using nanopillar compression test BS Kong, J Shin, GO Subramanian, J Chen, C Jang, Y Na, D Jang, ... Scripta Materialia 186, 236-241, 2020 | 17 | 2020 |
QIAN XIAOKorea Advanced Institute of Science and TechnologyΗ διεύθυνση ηλεκτρονικού ταχυδρομείου έχει επαληθευτεί στον τομέα kaist.ac.kr
