| Low cycle fatigue behavior of alloy 690 in simulated PWR water—Effects of dynamic strain aging and hydrogen JD Hong, J Lee, C Jang, TS Kim Materials Science and Engineering: A 611, 37-44, 2014 | 35 | 2014 |
| Effects of mixed strain rates on low cycle fatigue behaviors of austenitic stainless steels in a simulated PWR environment JD Hong, C Jang, TS Kim International Journal of Fatigue 82, 292-299, 2016 | 28 | 2016 |
| ENVIRONMENTAL FATIGUE OF METALLIC MATERIALS IN NUCLEAR POWER PLANTS–A REVIEW OF KOREAN TEST PROGRAMS C Jang, H Jang, JD Hong, H Cho, TS Kim, JG Lee Nuclear Engineering and Technology 45 (7), 929-940, 2013 | 28 | 2013 |
| Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage JS Kim, JD Hong, YS Yang, DH Kook Journal of Nuclear Materials 492, 253-259, 2017 | 23 | 2017 |
| 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 |
| Measurement of Zircaloy-4 cladding tube deformation using a three-dimensional digital image correlation system with internal transient heating and pressurization DH Kim, GH Choi, H Kim, C Lee, SU Lee, JD Hong, HS Kim Nuclear Engineering and Design 363, 110662, 2020 | 16 | 2020 |
| Effects of heat treatment on mechanical properties and sensitization behavior of materials in dissimilar metal weld HS Kim, J Shin, BS Kong, S Hong, S Oh, JD Hong, C Jang, S Lee International Journal of Pressure Vessels and Piping 172, 17-27, 2019 | 13 | 2019 |
| PFM application for the PWSCC Integrity of Ni-base Alloy Welds-Development and Application of PINEP-PWSCC JD Hong, C Jang, TS Kim Nuclear Engineering and Technology 44 (8), 961-970, 2012 | 11 | 2012 |
| Delayed hydride cracking assessment of PWR spent fuel during dry storage JD Hong, HC Kim, JS Kim, YS Yang, DH Kook Nuclear Engineering and Design 322, 324-330, 2017 | 8 | 2017 |
| Measurement of local mechanical properties for Cr-coated accident tolerant fuel cladding JD Hong, D Ahn, D Jang, H Oh, JY Kim, H Kim, M Ševeček Journal of Nuclear Materials 579, 154407, 2023 | 7 | 2023 |
| Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding JD Hong, M Park, AMA Holston, J Stjärnsäter, D Kook Journal of Nuclear Materials 543, 152596, 2021 | 7 | 2021 |
| Low cycle fatigue behavior of hot-bent 347 stainless steel in a simulated PWR water environment J Lee, MG Seo, JD Hong, TS Kim, C Jang Journal of Mechanical Science and Technology 30, 4931-4936, 2016 | 7 | 2016 |
| Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRs JD Hong, C Jang Proceedings of the ASME Pressure Vessel and Piping Division/K-PVP Conference …, 2010 | 6 | 2010 |
| The effects of dissolved hydrogen contents on the low cycle fatigue behaviors of a 316LN stainless steel in simulated PWR conditions PY Cho, C Jang, H Jang, JD Hong, TS Kim, JG Lee | 6 | 2010 |
| Enhanced crud resistance of CrAl coated ATF claddings in simulated PWR conditions SE Kim, DH Kim, JD Hong, JY Kim, HG Kim Journal of Nuclear Materials 578, 154357, 2023 | 5 | 2023 |
| Measurement and investigation of mechanical properties of a partial oxide dispersion strengthened Zircaloy-4 tube via an instrumented indentation test DH Kim, JD Hong, H Kim, J Kim, HS Kim, H Guim Materials Today Communications 27, 102210, 2021 | 5 | 2021 |
| Mechanical Property Degradation of Unirradiated Zircaloy-4 Cladding After Creep Deformation JD Hong, E Kim, YS Yang, DH Kook Nuclear Technology 203, 282-292, 2018 | 5 | 2018 |
| Environmental fatigue behaviors of Ni-base alloys in PWR primary water environments JD Hong, TS Kim, YS Lee, C Jang 2013 ICG-EAC, 2013 | 4 | 2013 |
| Study of the mechanical properties and effects of particles for oxide dispersion strengthened Zircaloy-4 via a 3D representative volume element model DH Kim, JD Hong, H Kim, J Kim, HS Kim Nuclear Engineering and Technology 54 (5), 1549-1559, 2022 | 3 | 2022 |
| Qualitative approach to understand fatigue behavior of CrAl-ODS-Zr alloy ATF cladding JD Hong, JY Kim 2021 KNS spring meeting, 2021 | 3 | 2021 |